气隙式膜蒸馏处理模拟放射性废水

对采用自制气隙式膜蒸馏装置净化处理质量浓度为1g/L Sr2+和离子质量浓度均为10g/L的Co2+、Sr2+、Na+、Ca2+四种离子混合模拟放射性废水进行了研究。结果表明:膜蒸馏技术对1g/L Sr2+料液中Sr2+截留率可以达到99.999%以上,去污系数(DF)在105以上;处理离子质量浓度均为10g/L的Co2+、Sr2+、Na+、Ca2+四种离子混合料液时,膜蒸馏对Sr2+、Co2+截留率均接近100%,DF(Sr2+)达1×106,DF(Co2+)达1×107;料液温度和料液流速对膜通量有一定影响,无论是提高料液温度,还是增加料液流速,均可以有效提高膜通量。在保证净化效果的情况下,在料液温度75℃,料液流速7L/min时,处理1g/L Sr2+膜通量可以达到4.15kg/(m2·h)。对离子质量浓度均为10g/L的Co2+、Sr2+、Na+、Ca2+四种离子混合料液进行处理时,膜通量也达到3.88kg/(m2·h)。     

纳滤处理重铀酸铵沉淀母液的研究

重铀酸铵沉淀母液是一种含常量硝酸铵的高盐分废液,目前主要采用硅胶吸附法进行处理,产生的二次废物量大。纳滤膜能透过硝酸铵等单价盐,而截留铀等以多价离子或大体积分子形态存在的组分。本文在铀浓度为40 mg/L、硝酸铵浓度为35 g/L的模拟重铀酸铵沉淀母液中,开展了纳滤技术处理重铀酸铵沉淀母液的研究。结果表明：在所筛选的4种商用纳滤膜中,NF270具有最优的综合性能;当跨膜压差为1.0 MPa、膜面流速为40 cm/s、料液温度为25 ℃时,NF270纳滤膜的铀截留率为97%,与之对应的透膜通量为60 L/(m²•h)。     

直接接触式膜蒸馏技术处理模拟放射性废液

采用聚丙烯中空纤维膜开展直接接触式膜蒸馏(DCMD)过程处理模拟放射性废液的研究,主要考察了料液温度、冷却水温度、料液流速以及冷却水流速的变化对膜通量和目标元素(Sr(Ⅱ)、Co(Ⅱ)和Cs(Ⅰ))截留效果的影响,并探讨了DCMD过程的传质传热机理。考察的四个运行参数中,料液温度的变化对膜通量的影响最大,料液温度由40℃增加至80℃,膜通量由2.7L/(m²·h)增加至29.2L/(m²·h)。此DCMD过程中,水蒸气在膜孔内的传质机理以努森-分子扩散为主,传质阻力主要来自于膜本身。在考察的料液温度(40～80℃)、冷却水温度(10～30℃)、料液流速(425～1 450mL/min)和冷却水流速(75～600mL/min)范围内,DCMD过程对Sr(Ⅱ)、Co(Ⅱ)和Cs(Ⅰ)的去污因子(DF)均保持在105以上。结果表明:DCMD过程对模拟放射性废液具有良好的处理效果,可作为一种新的放射性废液处理技术。     

乳状液膜技术回收处理含铀溶液中铀的研究

采用乳状液膜技术对含铀溶液中的铀进行回收处理,研究了制乳原料的最佳体积比,制乳时的搅拌速度、温度等因素,及回收处理铀时的温度、pH值、铀初始质量浓度、提取时间等因素对乳状液膜技术提取回收含铀废液的影响;探讨了乳状液膜提取回收铀过程中铀的迁移机理;通过热力学对乳状液膜技术提取回收铀的液膜传输过程进行了分析。结果表明,当制乳原料中P₂₀₄和液体石蜡的体积分数为0.1和0.05,Span80、磺化煤油与P₂₀₄的体积比分别为0.06、0.79,搅拌速度为2000 r/min,内水相盐酸的浓度为4 mol/L时,可制得稳定的油包水型乳状液膜。在常温常压、pH值2.5、铀初始质量浓度小于100 mg/L、含铀废液与乳状液膜的体积比为5时,用乳状液膜对铀废液提取0.5 h,铀的回收率可达到99%以上,Gibbs自由能ΔG<0,说明外水相的铀可自发地向内水相富集。     

气隙式膜蒸馏处理低放废液

低放废液在放射性废液里占有很大的比例,我国制定了严格的排放标准,尤其是对内陆核电站,需要选择更高效的处理技术,有必要研究膜蒸馏处理低放废液后的净化效果。基于气隙式膜蒸馏装置研究对模拟低放废水中微量的Sr~(2+)和Cs+的净化效果,以及温差和流速对净化效果的影响,对某乏燃料后处理厂里的低放废液进行处理。结果表明:膜蒸馏装置对微量的Sr~(2+)和Cs+平均截留率均大于99.99%,去污因子可以达到104量级以上;流速和温差对膜蒸馏装置的净化效果基本没有影响;对没有进行任何预处理后处理厂的低放废液,膜蒸馏装置连续处理4天多,处理后的馏出液的平均总α活度浓度为0.04Bq/L,平均总β活度浓度为15.13Bq/L,远低于该厂的排放标准。     

纳滤技术处理重铀酸铵沉淀母液的研究

正重铀酸铵沉淀母液是含常量硝酸铵的高盐分废液,目前主要采用硅胶吸附法进行处理,产生的二次废物量大。纳滤膜能透过硝酸铵等单价盐,而截留铀等以多价离子或大体积分子形态存在的组分,此外纳滤技术总体上还具有经济、二次废物量少、通量大等优势。本工作采用铀浓度为40mg/L、硝酸铵浓度为35g/L的模拟重铀酸铵沉淀母液,开展了纳滤技术处理重铀酸铵沉淀母液的研究。     

乏燃料连续溶解过程的动态仿真模型研究

本文通过分析乏燃料芯块与硝酸之间溶解反应的质量传递过程，以及溶解液中溶质的质量传递过程，基于质量衡算得到了乏燃料芯块溶解过程的动态溶解模型，并利用Comsol和Matlab软件建立了求解溶解模型的仿真程序。仿真结果表明，在温度90℃、硝酸进料浓度6 mol/L、进料流率11 L/min、回流量35 L/min的工艺条件下，溶解液需要270 min达到出料要求，而达到平衡所需时间为2 000 min。达到平衡后的溶解液出料中，铀浓度为253.23 g/L、硝酸浓度为2.78 mol/L,能满足出料要求。模拟结果的全过程质量平衡计算表明，模拟结果与理论计算值的相对误差为2.57%。模拟结果中溶质浓度变化趋势与实际过程基本一致，溶解器内铀浓度总体上呈先迅速升高、后较快减小、最后又缓慢减小，而硝酸浓度总体变化趋势则与铀浓度的变化趋势相反。以上结果表明，本研究所建立的回转式连续溶解器动态溶解仿真模型能较好地描述该溶解器中乏燃料的实际溶解行为，能为实际生产过程中乏燃料溶解工艺段提供仿真数据支撑。     

动态膜电解制备四价铀Ⅰ.装置建立及性能测试

以钛涂钌铱网为阳极、钛网为阴极,建立了动态膜电解制备四价铀装置,测试了该装置的性能,比较了使用国产膜和进口膜时的电解性能,同时还探讨了制备过程中各参数的变化。研究结果表明:该装置能在电流密度高达120mA/cm2的情况下稳定运行;隔膜采用贝斯特Nepem-417膜或旭化成Aciplex-F4112膜,对电解结果无显著差异;对于500mL铀质量浓度为199g/L的料液,仅采用72cm2的钛涂钌铱网为阳极、钛网作为阴极,电解180min,四价铀产率可达到93.1%;电解前后阴极料液中肼浓度从0.52mol/L下降为0.30mol/L,酸浓度从2.20mol/L下降为0.70mol/L,槽压在3～3.6V内变动,阴极电解液温度低于45℃(室温28℃)。     

铀同位素浓缩试验装置退役废水处理试验研究

铀试验装置退役废水含铀浓度高(133～4875mg/L),碱度大(182～1019mN/L).本研究采用沉淀、酸化去碳、吸附等工艺进行废水处理.先加入工业烧碱,在PH>13时废水中95%以上的铀可集中于沉淀中;再加入沉淀母液酸化去碳,在PH≈7时以5-6床体积/日的流速流经硅胶一树脂串联柱,出水含铀小于0.05mg/L,不用稀释即可排放.     

偕胺肟聚丙烯腈对铀酰离子吸附热力学及动力学过程分析

放射性含铀废水会带来环境污染风险,合理有效处理含铀废水十分必要。本研究通过吸附实验探究偕胺肟聚丙烯腈(AO-PAN)对U(Ⅵ)的吸附特性,系统研究吸附温度、初始浓度、吸附时间对AO-PAN吸附U(Ⅵ)的影响。结果表明,随着吸附温度升高,AO-PAN对U(Ⅵ)的吸附量逐渐增加,在343K温度时吸附量达201.6mg/g。不同温度条件下随着吸附时间增加,AO-PAN对U(Ⅵ)的吸附量逐渐升高,吸附初始时吸附速率较快,随着吸附逐渐进行吸附曲线逐渐趋于平缓,最终达到吸附平衡。AO-PAN对铀的吸附量随溶液中初始浓度的增加而升高,温度为303K,溶液中初始铀浓度为500mg/L时,AO-PAN对U(Ⅵ)的吸附量达305.8 mg/g。此外,AO-PAN对铀酰离子的吸附符合朗格缪尔(Langmuir)模型,吸附热力学分析表明AO-PAN对铀酰离子的吸附是吸热和自发过程,吸附动力学分析表明AO-PAN对铀酰离子的吸附行为遵循准二级动力学模型,吸附速率控制机理分析表明AO-PAN对U(Ⅵ)的吸附初始受颗粒内扩散过程控制,随着吸附不断进行吸附过程逐渐由颗粒内扩散控制变为液膜扩散过程控制。吸附实验结果表明,AO-PAN是一种优良的吸附剂,可以用于吸附废水中U(Ⅵ),吸附过程的模型方程可以用于AO-PAN对U(Ⅵ)吸附过程的分析和计算。     

Preparation of Zn/TiO2 powder and its photocatalytic performance for oxidation of P-nitrophenol

Zn-doped TiO2 catalysts were prepared using a sol-gel method and characterized by XPS,UV-Vis, BET, XRD in this study. Under the irradiation of simulant sunlight, the photocatalytic activity for the degradation of p-nitrophenol was studied too. After irradiation for 2.5 h, the degradation percentage of p-nitrophenol could rise to more than 80 %. The results showed that the spectrum absorption band edge of Zn/TiO2 powder does not broaden obviously comparing with pure TiO2 powder. Zinc exists as Zn （11）. When calcined at 973 K, there is a new phase as ZnTiO3 in Zn/TiO2 catalyst. The order of photocatalytic activity of Zn/TiO2 catalysts calcined at different temperatures for p-nitrophenol is 773 K 〉 673 K 〉 873 K 〉 573 K 〉 973 K and the photocatalytic activity of Zn/TiO2 catalyst calcined at 773 K is better than TiO2 catalysts heated at the same temperature, and outclasses that of commercial TiO2 catalyst. It also showed that the photocatalytic degradation of p-nitrophenol follows first-order kinetics under the irradiation of simulant sunlight.     

Current status of radiation therapy for prostate cancer

Radiotherapy for the treatment of prostate cancer has been extensively explored in the past. Along with the comprehensive understanding of the biology of prostate cancer and rapid advances in terms of technology, the out- come of treatment for the patients with prostate cancer has improved. The authors review radiotherapy as the primary treatment for the disease, with particular emphasis on the technological advances from both the radiobiological and radiophysics aspects. Nonconventional fractionated irradiation like hyper- or hypo-fractionation has been imple- mented in the clinic, the final results still need to be confirmed in the future. Technological advances like IMRT, IGRT, in the last two decades have significantly improved the delivery of external radiotherapy to the prostate. This has re- sulted in an overall increase in the total dose that can be safely delivered to the prostate, which has led to modest im- provements in the biochemical outcome. However, establishing the standard therapy for prostate cancer remains con- troversial. It is hoped that the next decades will bring continued advances in the development of biologicals that will further improve current clinical outcomes.     

The control system for SSRF injection and extraction

This paper introduces the injection and extraction control system design for SSRF,which is a distributed control system aimed at stability and reliability of the pulse power supplies,PPS(Personnel Protection System)and MPS(Machine Protection System).The hardware environment is mainly based on PLC(Programmable Logic Con- troller),and ARM(Advanced RISC Machine)is also applied for studying stability of the power supplies.WinCC and EPICS(Experimental Physics and Industrial Control System)have been selected as the platforms of SCADA(Super- visory Control and Data Acquisition).For unifying the interfacing to the control computer,all front-end equipments are connected via Industrial Ethemet.     

水平管内含空气蒸汽强制对流冷凝换热模型研究

为研究含空气蒸汽在水平管内强制对流冷凝换热特性,基于对传热传质过程的分析,建立了管内为环状流与波状流条件下的流动冷凝换热模型。从潜热、显热和液膜3个环节对整个换热过程进行建模,最终得到计算局部冷凝换热系数的理论关系式。模型预测结果与实验数据的对比表明,二者相对偏差在±20%以内,验证了该换热模型的准确性与适用性。通过进一步的研究发现：从换热管入口至出口,随着冷凝的进行,管内换热主要热阻由液膜热阻向气液界面的凝结热阻转变;主流气体对流换热过程基本可忽略。     

Investigations on landmine detection by BF3 detector

Experiments were carried out to investigate the possible use of neutron backscattering for the detection of polyethylene (PE) sample buried in the soil. In detection of landmine by neutrons, the neutron detector and its shield play an important role. In this paper, the effects of graphite, heavy water, polyethylene and boric acid moderators on the flux of back scattered neutrons were investigated. We have also experimentally verified the effect of BF3 detector shield and obtained good agreement with theory.     

Web Services interface of SSRF archive data analysis system

Accelerator database stores various static parameters and real-time data of accelerator. SSRF (Shanghai Synchrotron Radiation Facility) adopts relational database to save the data. We developed a data retrieval system based on XML Web Services for accessing the archive data. It includes a bottom layer interface and an interface applicable for accelerator physics. Client samples exemplifying how to consume the interface are given. The users can browse, retrieve and plot data by the client samples. Also, we give a method to test its stability. The test result and performance are described.     

有效探测面积大于1000 cm2的正比计数器测量系统性能测试

为对自制的活性面积高达1 000 cm²的大面积源进行表面发射率定值,同时作为现有2πα、2πβ表面发射率标准装置能力的扩充,研制了一套内置式大面积2π多丝正比计数器测量系统,并利用活性区直径为8 mm的²⁴¹Am点源及活性区面积为10 cm×15 cm的大面积²⁴¹Am和⁹⁰Sr-⁹⁰Y源对其进行计量学性能测试。结果表明：计数器内计数响应均匀性优于±0.4%,有效探测面积达1 400 cm²;所得²⁴¹Am源高压坪曲线的坪长为1 400 V,坪斜为0.27%/100 V,坪区内计数变化为0.87%;⁹⁰Sr-⁹⁰Y源高压坪曲线的坪长为300 V,坪斜为0.75%/100 V,坪区内计数变化为0.80%;10次测量重复性好于0.4%,8 h内短期稳定性好于0.3%,1 a内长期稳定性好于0.8%。     

Assessment of radioactivity levels in some oil samples from the western desert, Egypt

Distributions of natural gamma-emitting radionuclides were determined in 93 oil samples collected from some petroleum fields in the western desert of Egypt. The radioisotope activities in the area under investigation lay in the range of (21 ± 4) to (38 ± 13) Bq?L-1 for 226Ra, (9 ± 2) to (15 ± 5) Bq?L-1 for 232Th, and (154 ± 28) to (303 ± 54) Bq?L-1 for 40K. The mean values were 27, 12, and 201 Bq?L-1, respectively. Among oils, variations in radionuclide ac- tivities could be on account of differences in TDS, HCO3, and Ba, with high or low pH. In this environment, oil prop- erties differently affected the mobilization of natural radionuclides. The range of 226Ra variation had been compared with available data from other countries. The calculated absorbed dose rate ranged from 22.33 to 32.66 nGy?h-1 in lo- cation (B) and (E) respectively, which was less than the accepted value.     

Preparation and properties of 117m Sn(IV)-TTHMP in in-vitro and in small animals

In this work,TTHMP was synthesized and labelled with 117m Sn.The preparation conditions,stability and lipophilicity of 117m Sn(IV)-TTHMP were investigated.Biodistribution of the complex in rabbits and mice was studied.It was found that the quantity of TTHMP and pH value of the prepararion solution had vital effects on the labeling yield of 117m Sn(IV)-TTHMP.It was also found that 117m Sn(IV)-TTHMP was hydrophilic and stable at room temperature and 37℃ in open air 117m Sn(IV)-TTHMP showed unexpectedly high bone uptake and bone-to-blood ratio in the animals.This made it potentially useful as an reagent for skeletal scintigraphy and radiotherapy of bone tumors.     

The role of AGFA high-energy CR in the calibration and quality control of multileaf collimators （MLC）

Linear accelerators equipped with multileaf collimators （MLC） are becoming more common and are widely used in the intensity-modulated radiotherapy （IMRT）. There is an imperative need to ensure the commissioning specification of the linear accelerators for the sake of quality assurance （QA） and quality control （QC）. This paper is aimed to investigate the role of AGFA high-energy CR （Computed Radiography） in calibrating dynamic multileaf collimators and evaluating the accuracy of the leaf position. The result shows that AGFA high-energy CR can easily and conveniently be used to calibrate MLC and verify its position. Hence, the application of AGFA high-energy CR is proved to be an accurate and time-saving method for routine MLC QC, especially when MLC calibration adjustments are required.