Objective To evaluate the efficacy of ultrasound-guided sacral block in the obese patients by comparing it with the traditional positioning method.Methods Sixty obese patients,aged 25-50 yr,weighing 56-80 kg,with body mass index ≥ 30 kg/m2,scheduled for elective anorectal surgery,were randomly divided into 2 groups (n =30 each) using a random number table:ultrasound-guided sacral block group (group U) and traditional positioning method group (group T).The sacral canal puncture point was located via either ultrasonic or traditional positioning method.After successful puncture,1％ lidocaine 20 ml was injected.The number of patients in whom puncture was successful at first attempt and the number of patients in whom the time for puncture ≤ 1 min were recorded.The adverse reactions were observed.The efficacy of sacral block was evaluated.Results Compared with group T,the success rate of puncture at first attempt was significantly increased (P ＜ 0.05),and no significant changes were found in the number of patients in whom the time for puncture ≤ 1 min or efffcacy of sacral block in group U (P ＞ 0.05).No adverse reactions were found in the two groups.Conclusion Ultrasound-guided sacral block can raise the success rate of puncture at first attempt and provide similar efficacy of block in the obese patients when compared with the traditional positioning method,and thus has significant clinical value.

Objective To develop the method of analyzing α-radionuclides using large area grid ionization chamber.Methods Ultrasonic dispersion and vacuum drying system was used to prepare sample source,large standard thin source and plutonium plane source were used to optimize the working condition of spectrometer,and calibrate the instrument for analyzing α emitters.The certified reference materials (GBW04127) were used to verify the accuracy of the method.Results The non-linearity of calibration curve for standard thin sources of neptunium,plutonium and americium was less than 0.2％,and the resolution were 112,84 and 106 keV,respectively.The counting efficiency was 31.2％ for the large standard thin source.The values of specific activity measured in this way were in good agreement with those of the certified reference materials.232Th,238U,230Th,234U/226Ra,210Po,222Rn and 218Po were analyzed in a uranium mineral sample,and their specific radioactivity values were 5.3,3.8,35.6,21.4,27.0,19.6 and 11.1 Bq/g,respectively.Conclusions The method can be used to analyze α spectrum quickly in low-level radioactive environmental samples.

Objective To establish a method of analyzing total uranium and 235U/238U ratio in urine using inductively coupled plasma mass spectrometry (ICP-MS) and uncertainty assessment.Methods Urine sample was digested with HNO3 and H2O2,and total uranium was determined using ICP-MS method directly.The digested urine sample was separated to concentrate uranium with tributyl phosphate (TBP) column,and 235U/238U ratio was analyzed using ICP-MS.The uncertainty was evaluated through sample pre-treatment,measurement and standard curve calculation.Results The recovery of total uranium in urine was 98.4％-102.4％,detection limit was 0.002 μg/L.The relative expanded uncertainty of total uranium concentration in urine was 0.26 (k =2).235 U/238 U ratio was 0.001 1 (k =2).Conclusions This study offers a low detection limit,good recovery and precision method for rapid determination of total uranium and 235U/238 U ratio in urine samples.It is potential used for both in occupational exposure assessment and nuclear emergency situation.The uncertainty evaluation of total uranium and 235U/238U ratio in urine are reliable.

Objective To analyse the nutrients of Acaudina leucoprocta and explore its hypolipidemic effect. Method The nutrients constituents of Acaudina leucoprocta were analyzed by high-performance liquid chromatography,and was compared with Apstichopus japonicus. The hyperlipidemia model was estabolished by feeding SD male mice with high fat feed. The change of liver index and fat coefficient as well as the effects on serum lipid,antioxidant capacity of serum in rats were observed. Results The fat content of Acaudina leucoprocta was only 0.43%,significantly lower than that of Apstichopus japonicus. The content of amino acids in Acaudina leucoprocta was higher than that of Apstichopus japonicus. Acaudina leucoprocta would decrease the liver index,fat coefficient and TC,TG,LDL-C,LDL-C/HDL-C in serum significantly,and increase HDL-C and HDL-C/TC. MDA and NEFA contents were effectively reduced. GSH-Px activitives were enhanced. Conclusion Acaudina leucoprocta is very rich in protein,and low in fat content. It has hypolipidemic and antioxidative effects,and may reduce the oxidative damage caused by high fat diet. Acaudina leucoprocta may be used as a functional food.

Objective To optimize the enzymolysis condition for Acaudina leucoprocta to research lencoprocta the antioxidant activity of its hyoholysate in vivo.Method Response surface methodology (RSM) was employed to optimize the hydrolysis conditions with protamex.The ICR mice were given ig the hydrolysate of Acaudina lencoprocta obtained under optimal conditions.The activity of superoxide dismutase (SOD) and glutathione peroxidase (GSH-Px) and the content of MDA in blood serum and liver in mice were analyzed.Results and Conclusion The best hydrolysis conditions were:the amount of enzyme was 2.02%;enzymolysis temperature was 51.18 ℃;enzymolysis time was 127.81min,hydroxyl radical scavenging rate was 73.10%.The activities of SOD,GSH-Px in hydrolysate were significantly enhanced and the content of MDA was significantly lower,which showed that this hydrolysate had remarkable antioxidation activity.So the enzymolysis technology for Acaudina leucoprocta was optimal.

Objective To develop a rapid and reliable method for determination of 210Po using large-area grid ionization chamber α spectrometry.Methods Samples were digested using a microwave digestion system.After preparation of sample source,the concentration of 210Po in clam was detected by large-area grid ionization chamber (φ 25 cm).209Po tracer was used to obtain the recovery.Results Large-area grid ionization chamber could achieve better counting and α spectrum resolution when the optimized thickness was 250 μg/cm2.By spiking 209Po tracer in clam,the minimum detectable activity was 9.870 × 10 4 Bq and the recovery of 210Po was 98％.Conclusions Compared with the traditional method,the developed method can avoid separation process,using less quantity of sample (0.2-0.5 g dry) and simplify the measurement process.This method may be has broad application prospects.

Objective To ascertain the uranium isotopic ratios in surface water samples around nuclear power plants.Methods Water samples were collected in Jiangsu,Shandong and Zhejiang provinces.An efficient separation procedure for the trace uranium concentrated from surface water by tributyl phosphate (TBP) was used.Inductively coupled plasma mass spectrometry (ICP-MS) was applied to determination of low abundance uranium isotopes.Results The 234 U/238 U isotope ratio varied from 4.575 × 10-5to 7.752 × 10-5 and 235U/238U from 7.273 × 10-3 to 7.639 × 10-3.Conclusions The 234U is enriched in the surface water.

Objective To ascertain the uranium concentrations and uranium isotopic ratios in drinking water in Xilingol League,the Inner Mongolia Autonomous Region.Methods Drinking water samples were collected in Xilingol League,the Inner Mongolia Autonomous.Region inductively coupled plasma mass spectrometry (ICP-MS) was applied to determine the concentration of uranium and uranium isotope abundance.Results The uranium concentrations in all samples were in the range of 2.73-18.9μg/L,with an average of 8.20 μg/L.Tbe234U/238U isotope ratio varied from 7.513 × 10-5to 3.003 × 10-4 and235U/238U from 7.196 × 10-3 to 7.391 × 10-3.The relative standard deviation (RSD) was less than 0.5％ for234U/238U and 0.2％ for235 U/238U.Conclusions The uranium concentration in samples collected from Dongwuqi was high than 15 μg/L,whih is the limit given by World Health Organization (WHO).The uranium in drinking water originates from the natural environment.The234U is enriched in drinking water.

Objective To establish an effective and reliable method for analysis of uhratrace uranium in multi-stage atmospheric particles providing the monitoring and evaluation of the content of radioactive uranium in the atmosphere.Methods A large volume six-stage-impactor sampler of atmosphere particles was used to collect aerosol samples,and uhratrace uranium in particles was digested using microwave and measured by inductively coupled plasma mass spectrometry.The filter material,digestion conditions and microwave digestion system had been optimized.Results The background of uranium level on the cellulose filter was the lowest,and the samples were digested by using HNO3-HCI (aqua regia)-H2O2 solution.Reference material SRM2783 was used to validate the accuracy of the method,and the relative error of the 238U was 7％,The detection limit of the method was 2 × 10-4ng/m3.The aerosol actual samples were analyzed using the established method.The mass concentrations of uranium in PM2.5 was in the range of 0.023-0.065 ng/m3.Conclusions The established method was effective and reliable to monitor the concentration level of ultratrace uranium in multi-stage atmospheric particles.

Objective To investigate the activity concentration of 90St in tea produced in Chinese typical regions,enrich the baseline data for 90Sr level in Chinese tea,and evaluate possible exposure doses to people.Methods Samples were carbonized,ashed,digested and leached,and then extraction chromatography method was used to separate 90Sr and 90y.After preparation of sample source,radioactivity of 90Y was measured using low-level α/β counter.Results Twenty six kinds of tea produced in 16 typical regions from 26 cities of 16 provinces were collected in 2016,and their 90Sr activity concentrations were analyzed using the separation method of di (2-ethylhexyl) phosphate (HDEHP) extraction chromatography.The results revealed that the activity concentrations in 26 kinds of tea samples ranged from 0.28 to 3.78 Bq/kg,and contributed possible exposure doses of 0.44 × 10-2-6.00 × 10-2 μSv to each people.Conclusions These doses were far less than the ICRP annual dose limit of 1 mSv for the public,suggesting less impact on people's health.