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Objective To explore the electrophysiological examination results and risk factors of type 2 diabetic peripheral neuropathy. Methods 337 patients with type 2 diabetes from August 2014 to December 2016 in the first people's hospital in Shizuishan city were divided into DPN group (n=218) and NPDN group(n=119) according to the results of NCV and SSR examinations. The general information and laboratory biochemical indicators in the two groups were compared. Multivariate Logistic regression was used to analyze the risk factors of DPN. Results The diagnosis rate of DPN detected by NCV combined with SSR was higher than that of NCV or SSR alone(P<0.05);There were significant differences in age,duration of diabetes,history of hypertension,systolic blood pressure,2h FBG,HbA1c,FINS,2 h INS,FC-P, 2h FC-P,ACR between the DPN group and NPDN group(P<0.05);Logistic multivariable analysis showed that age, duration of diabetes, 2h FBG, HbA1c, ACR were independent risk factors for DPN. Conclusion It is beneficial to increase the diagnosis rate of DPN by NCV combined with SSR. There is a higher incidence rate of DPN type 2 diabetes patients with older grade, longer duration of diabetes, higher 2h FBG, HbA1c and ACR.
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Objective To survey the 238U radioactivity level in the surface soil in the Beijing-Tianjin-Hebei Border (BTHB) region,and to prepare a high resolution distribution map of 238U activity concentrations.Methods The soil samples were collected in a grid (10 km × 10 km).The activity concentrations of 238U in soil samples were measured by using HPGe γ spectrometry.The distribution of the activity concentrations of 238U in soil samples was mapped by the aid of MAPGIS software.Results In total,416 samples were collected and measured.The activity concentrations of 238U were in the range of 0.1-106.0 Bq/kg,with an average of 34.7 Bq/kg.The 238U activity concentration distribution map showed that 238U activity concentration was in the range of 15-55 Bq/kg mostly on the surface soil in the BTHB region.Conclusions The map of 238U activity concentration shows the distribution of 238U activity concentration in the BTHB region.It is of importance to map the distribution of 238U activity concentration in the BTHB region,by converting a huge amount of data into the simple and intuitive graphics,and for evaluating the regional environmental radioactivity and studying the radioactive substance migration within the locality.
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Objective To determine the activity concentration of radionuclides for 137Cs and 40K in edible wild mushrooms,and to evaluate the extent of radioactive contamination and ingestion doses to adults from consumption of these wild mushrooms.Methods A total of 33 samples for 18 edible wild mushroom species were collected from natural forest Mangshi,Yunnan province.The activity concentrations of 137Cs and 40K were analyzed by using high-purity germanium (HPGe) gamma spectrometry.Results Except.for one sample that was below the MDA,137Cs artificial radionuclides were detected in other 32 samples,with activity concentration of 137Cs in the range of 0.45-339.58 Bq/kg (dry weight) and an average of 25.47 Bq/kg (dry weight).In regards to 40K in edible mushrooms,all species presented the activity concentrations for this radionuclide and the levels varied from 453.4 to 1 882.6 Bq/kg (dry weight),with an average of 815.1 Bq/kg (dry weight).After species of mushroom with only one sample were eliminated,there was significant difference for 137Cs(F =21.13,P ＜ 0.05) among 6 species of mushroom named Gomphus floccosus (Schw.) Sing.,Boletus edulis bull,Boletus edulis bull,Tylopllus bolloul (Peck) Sing.,Lentinus edodes (Berk.) Sing.and Boletus brunneissimus W.F.Chin,but without significant difference for 40K.Conclusions These 6 different mushroom species have different capacity to retain radionuclides of 137Cs in soil.These wild mushrooms,such as Gomphus floccosus (Schw.) Sing.and Lentinus edodes (Berk.) Sing.have large affinity ability for radionuclides137Cs.The effective dose to adults attributable to consuming these kinds of mushrooms is small and below the level that could cause harm.
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Objective To determine the artificial radionuclides levels in environmental samples collected in some areas of China following the Japanese Fukushima nuclear accident,and to evaluate the extent of radioactive contamination.Methods A total of 118 samples including aerosol,water,soil and biological samples were collected and the activity concentrations of 131I, 137Cs and other artificial radionuclides were analyzed by using high-purity germanium (HPGe) γ spectrometry.Results Artificial radionuclides 131I,134Cs,137Cs and 136Cs were detected in the aerosol samples on 2 April,2011 and the activity concentrations were 1720,247,289,and 23 μBq/m3,respectively.Trace amount of 131I was detected in one sample of rain water and two samples of surface soil with concentrations of 2.08 Bq/L,1.82 and 0.59 Bq/kg,respectively.131I was also detected in 18 vegetable samples which were collected from 2 April to 13 April with the range of 0.55 -2.68 Bq/kg.Neither abnormal concentrations of 131I nor 137Cs was detected in milk,drinking water,sea water and marine products samples.Conclusions During the Fukushima nuclear accident,although minute quantities of radionuclides were detected in some samples collected in China,the effective dose for adults attributed to the nuclear accident is extremely small and significantly below the level that could cause harm to the public.
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Objective To detect artificial radionuclide content in the spinach and soil in open air vegetable garden in Beijing during Fukushima nuclear accident and to study the radioactive contamination characteristics of the samples.Methods 6 spinach samples and 3 soil samples in open air vegetable garden were obtained through continuously sampling.High-purity germanium (HPGe) γ spectrometry was used to analyze activity concentrations of artificial radionuclide131 Ⅰ etc in these samples.Results Artificial radionuclide 131Ⅰ was detected in the 6 open air spinach samples.Artificial radionuclide 137Cs was detected in 3 vegetable garden soil samples,trace amount of 131 Ⅰ was detected in 1 open-air surface soil sample alone.Conclusions Following the Fukushima nuclear accident,spinach in Beijing's open-air vegetable garden was slightly polluted by artificial radionuclide 131 Ⅰ,with the highest values of pollution appeared around April 4,2011,but it could not cause harm to human health.
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Objective To explore the effeetiviness of the method of LabSOCS(Laboratory sourceless calibration software)efficiency calibration in laboratory rapid analysis for emergency monitoring of nuclear incidents.Methods The detection efficiency of three kinds of environmental samples in emergency monitoring Wag calculated bY using the LabSOCS efficiency calibration method,and compared with the values that were obtained by way of radioactive source calibration method.Results The maximum relative deviation of the detection efficiency between the two methods was less than 15%,and the values with relative deviation less than 5%accounted for 70%.Conclusions The LabSOCS efficiency calibration method might take the place of radioactive source efficiency calibration method,and meet the requirement of rapid analysis in emergency monitoring of the nuclear incidents.
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Objective To test a full range of processes of sample collection,preparation,measurement and analysis by conducting the intercomparison of gamma-ray spectrometry measurement and analysis of radionuclides among key laboratories,so as to facilitate the development of gamma-ray spectrometry measurement and analysis technology.Methods To complete the collection and preparation of soil samples by Chinese Center for Disease Control and Prevention (CDC) laboratory and to measure and analyze the content in two soil samples of 214Pb,214Bi,208TI,228Ac,40K and 137Cs by three laboratories using gamma-ray spectrometry.Results The value calculated by any two laboratories were less than 1 in terms of assessment standards agreed by these three laboratories and based on the activity concentrations and the total uncertainty reported from them.The measurement results from our lab were acceptable.Conclusions Measurement results from these three laboratories are in agreement to some extent.This intercomparison activity has tested the analytical ability of the three laboratories and raised the level of our laboratory in testing homogeneity of sample preparation.
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Objective To measure the current environmental radioactivity levels in some districts of Yunnan Province,and to estimate the external doses to local residents.Methods The surface soil,aerosol and water samples were collected and analyzed by HPGe gamma spectrometry.Based on the estimation model selected by Ministry of Health in the nationwide soil survey,the doses to local residents from 238U,226Ra,232Th,40K and 137Cs in environmental samples were estimated.CARI-6 software issued by FAA (Federal Aviation Administration ) was used to estimate cosmic radiation dose to the local population.Results The external annual dose rate to the local people was 1.13 mSv per year,of which 0.52 mSv per year was contributed by natural radionuclides in soil,0.6 μ Sv per year by 137 Cs in soil and 0.61 mSv per year by cosmic radiation.Conclusions The cosmic radiation and natural radionuclides in soil might contribute 99.95％ of external exposure dose,while artificial radionuclide 137Cs contribute 0.05％ of external exposure dose.
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Objective To develop a radionuclide parameter database on internal contamination in nuclear emergencies. Methods By researching the radionuclides composition discharged from different nuclear emergencies, the radionuclide parameters were achieved on physical decay, absorption and metabolism in the body from ICRP publications and some other publications. The database on internal contamination for nuclear incidents was developed by using MS Visual Studio 2005 C# and MS Access programming language. Results The radionuclide parameter database on internal contamination in nuclear emergency was established. Conclusions The database may be very convenient for searching radionuclides and radionuclide parameter data discharged from different nuclear emergencies, which wonld be helpful to the monitoring and assessment of internal contamination in nuclear emergencies.
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Objective To compare the cosmic radiation doses to air crew (including pilots and flight attendants) between polar route and non-polar route flights. Methods A typical polar flight route (Beijing-New York) was selected and compared with non-polar route, non-polar route was selected as control group. Optically stimulated luminescence (OSL) dosimeter and CR-39 solid track detector were used to measure the cosmic radiation dose to air crew. Results The annual mean effective dose to air crew from polar route and non-polar route was (5.79 ± 0.92)mSv/a and (2.14 ± 0.64)mSv/a, respectively.The 1000 h effective dose to air crew was (3.10 ± 0.27)mSv/kh and (2.21 ± 0.46)mSv/kh,respectively. There was significant difference between the two groups in either annual mean effective dose (t=30.25, P＜0.05) or 1000 h effective dose (t =7.60, P＜0.05). The doses of pilot groups were higher than that of flight attendants for either polar route ( t = 7.96, P ＜0.05) or non-polar route (t=4.70, P ＜ 0.05). Conclusions The effective dose to air crew from galactic cosmic radiation during polar route fight might be higher than that of non-polar route fight, however, it did not exceed 20 mSv/year,which is the limit of national standard.
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Objective To describe a simplified generic procedure to evaluate the external exposure dose evaluation in radiological emergency, and to compile the corresponding computer software. Methods Based on the related reports of IAEA, this generic procedure of external exposure dose evaluation in radiological emergency was compiled to computer software by Visual Basic 6.0. Results The generic procedure for evaluation of external exposure dose could be used in the external exposure radiation accident emergency. The actual accident data were input in this software, then the results from this software agreed with those of the actual accident well. The maximum error was 40% , and the minimum error was 6%.Conclusions The generic procedure for evaluation of external exposure dose could provide practical emergency response guidance. The software might help to evaluate the accidental dose more quickly and accurately, and provide scientific basis to take the immediate response actions.
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Objective To assess the accuracy and precision of γ-spectrometry analysis, and to obtain accurate and valid measurement results in the middle term and long term. Methods A nationwide intercomparison on gamma-ray spectrometry measurement of activity concentration of 226Ra, 232Th and 40K in soil and building material was organized by National Institute for Radiological Protection( NIRP) , China CDC. Results 15 laboratories participated in this intercomparison, with 13 laboratories produced acceptable results. Only 2 laboratories were classified as " not acceptable" , including one for inappropriate accuracy in determination of 40K and another for inappropriate precision determination of 226Ra in both kinds of the samples. Through comment and discussion, the second round intercomparison got satisfactory results. Conclusions The overall measurement results of samples for intercomparison are in close agreement with the reference values. Most of the laboratories involved in the intercomparison have good ability in γ-spectrometry analysis.
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Objective To organize measurement comparison among provincial CDC gamma spectrometry laboratory for verification of the precision and accuracy of the measuring results from each laboratory and to improve the ability and level for radionuclides measurement in building materials.Methods The method for gamma spectrometry measurement comparison was referred to the method of IAEA international comparison in 2002.Results The results of these labs in this comparison agreed with the reference results well.About 50% labs' relative biases were less than 5%,over 80% labs were less than 10%.Conclusions The results of this comparison showed that the analysis method for the radioactivity content in building materials by gamma spectrometry in each lab was credible and meet the request of the standard GB 6566-2001 "Radioactive Nuclide Limit for Building Materials".
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Objective To estimate the dose to non-uranium miners from external exposure.Methods Ore samples of non-uranium mines were collected in site and analyzed with gamma spcetrometry,then annual dose to the miners was estimated based on the measured radioactivities of radionuclides.Results Thirty-two ore samples in thirteen mines in seven provinces were collected and analyzed.Among them,radioactivity concentrations in two samples were higher than others,and the annual doses from external exposure to the radionuclides in the two ore samples were estimated to be higher than 1 mSv/a.Conclusions Gamma spectrometry is fit for determining the radionuclides concentrations and its results can be used for estimating dose from external exposure in non-uranium mines.
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Objective To establish a method for estimating internal dose from aerosol inhalation in non-uranium miners.Methods Aerosol samples in a tunnel in Dongchuan Copper Mine in Yunnan Province were collected by portable high flux air sampler.Radionuclides collected at the sampler filters were analyzed by the gamma spectrometry.Annual committed effective dose due to inhalation of the aerosol dust was estimated using the formula provided by ASTM.Results Radionuclides collected in two aerosol samples were anlayzed,the annual committed effective doses due to inhalation of 1 μm and 5 μm aerosol were estimated.Conclusions The method of using high flux air sampling and gamma spectrometry is explored to estimate the dose from aerosol inhalation.
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Objective To develop the software for the assessment of radionuclide concentration and doses from atmospheric dispersion. Methods Based on procedures for radionuclide atmospheric dispersion and dose assessment in IAEA publications (safety series reports No. 19), a parameter database was constructed using Microsoft Access, and the dispersion model and dose assessment methods were computerized using Microsoft Visual Basic 6.0, then we got the dose assessment software for radionuclide atmospheric dispersion. Results Atmospheric radionuclide concentration and public effective dose in a year could be estimated rapidly with the present software. Conclusion The present software provides a practical and rapid tool for evaluation and assessment the influence of radionuclide atmospheric dispersion, which can be used in the evaluation of atmospheric radionuclide concentration in routine monitoring or nuclides/radiological emergency, and also can be used as the screening evaluation in environmental surveillance.