几种矿物材料对Cs+吸附性能的研究

通过几种矿物材料对Cs 吸附性能的研究,采用间歇法对优选出的合成沸石(ZF)研究其在不同环境条件下(浓度、温度、pH、模拟地下水)对Cs 的吸附性能,为评价中低放核废物处置效果提供一些参考数据。结果表明,ZF对Cs 的平衡吸附容量随Cs 溶液浓度的升高而增大,平衡吸附比随Cs 溶液浓度的升高而降低;平衡吸附容量、平衡吸附比随水相温度的升高而降低;在pH=5~9范围内,pH值对其吸附性能影响不大,但当pH=11时,ZF的吸附性能发生了明显的下降;在不同模拟地下水中,ZF的吸附性能随模拟地下水中化学组成不同而不同;其吸附平衡时间大约在10~15 d。     

4A沸石对Sr2+的吸附性能的研究

采用间歇法研究在不同环境条件下（浓度、pH值、介质、温度），4A沸石（简称四）对Sr^2＋的吸附性能影响。结果表明：ZF对Sr^2＋的吸附性能比较好，当Sr^2＋浓度为0．05mol/L时，ZF对Sr^2＋的吸附平衡时间约在14天左右，平衡吸附量为526mg／g。Sr^2＋的浓度对ZF的吸附性能影响比较大，其次是溶液的pH值、介质和溶液的温度。ZF对Sr^2＋的平衡吸附量随Sr^2＋浓度的升高而增大，但平衡吸附率和平衡吸附比随着浓度的增大而降低。pH值增大时ZF对Sr^2＋的吸附性能加强。介质溶液含种类、浓度不同的离子时，相对于去离子水介质，ZF对Sr^2＋吸附性能有程度不同的下降；但腐殖酸的存在可以削弱这种影响。温度升高时，ZF对Sr^2＋吸附性能降低。     

合成沸石对Sr~(2+)的吸附性能及其表征

采用间歇法研究了合成沸石(ZF)在不同环境条件下对Sr2+的吸附性能,并对吸附Sr2+后的ZF用X-衍射(XRD)表征和分析,为评价中低放核废物处置效果提供参考依据。实验表明:ZF对Sr2+的吸附性能比较好,ZF对Sr2+的吸附平衡时间约在5～14 d。Sr2+溶液的浓度对ZF的吸附性能影响比较大,其次是介质、溶液的温度和溶液的pH值。ZF对Sr2+的平衡吸附量随Sr2+溶液浓度的升高而增大,但平衡吸附率和平衡吸附比随着溶液浓度的增大而降低。pH值增大时,ZF对Sr2+的吸附性能也提高。由于介质溶液中离子种类、浓度以及其他成分不同,所以ZF对Sr2+的吸附能力有差异。温度升高时,ZF对Sr2+吸附性能提高。从总体上说,在溶液中Sr2+浓度为0.005 mol/L时,ZF对Sr2+吸附性能受溶液的pH值、介质和溶液的温度影响不大,吸附Sr2+后ZF的晶胞参数是减小的。     

大亚湾核电站处置场天然屏障对85Sr、134Cs和60Co的吸附性研究

通过静态实验和动态实验,研究了85Sr、134Cs和60Co在大亚湾核电站中低放废物处置场近场钻井岩芯样和探槽样中的迁移分布规律.静态实验结果显示,同一种土样对3种核素的吸附比差异很大,说明该地地质介质对核素的吸附具有选择性.3种核素的吸附平衡时间为120 h,分配系数Kd的平均值分别为9.4×10 mL/g(85Sr)、2.3×103 mL/g(134Cs)和1.3×102 mL/g(60Co).动态实验结果给出了3种核素的延迟系数Rd的平均值分别为7.4×102(85Sr)、1.8×104(134Cs)和1×103(60Co),表明85Sr在土柱中的迁移比134Cs和60Co的快.     

静态批示法研究铯在新疆托克逊粘土上的吸附分配比

采用静态批示法研究了Cs在新疆托克逊粘土上的吸附行为,分析了平衡时间、pH、固液比利粘土粒度对Cs在粘土上吸附性能的影响.结果表明,Cs在粘土上约7天达到吸附平衡,吸附分配系数Rd为487 mL·g-1,Cs的吸附分配比随固液比、粘土粒度、液相铯浓度的增大而减小,随pH增大而增大,计算得Cs在粘土层中迁移速率为0.214 m·a-1.结果表明,粘土对铯的吸附能力较强,粘土是核废物处置的较好的备选回填材料.     

~(110m)Ag和~(137)Cs在海洋沉积物中分配系数研究

采用静态批式法研究了吸附时间、固体浓度及核素浓度对放射性核素110mAg和137Cs在海洋沉积物中分配系数的影响。结果表明,110mAg在海洋沉积物中的吸附平衡时间约7天,137Cs在海洋沉积物中的吸附平衡时间约10天;在低浓度条件下110mAg和137Cs在海洋沉积物中的吸附等温线趋近于线性,即核素分配系数不随核素浓度的增加而改变;当固体浓度在0.25~10 g/L时,两核素分配系数均随固体浓度的增加明显减小,而固体浓度达到一定上限后(10 g/L),核素分配系数不再随固体浓度的增加而改变。     

放射性铯在沸石中的吸附与迁移的研究

研究了~(134)Cs在沸石中的吸附与迁移行为.用间歇法测定了~(134)Cs(作为~(137)Cs的示踪剂)在斜发沸石和丝光沸石等4组地质样品上的吸附比(R_d);研究了接触时间、沸石颗粒度、固液比、pH值和核素浓度对吸附比的影响,测定了吸附等温线和铯的吸附容量.用柱实验法研究了~(134)Cs在沸石柱中的吸附与迁移行为,测定了~(134)Cs在柱中的迁移分布.结果表明,沸石对Cs的吸附能力很强,对Cs而言,沸石是核废物处置的很好的回填材料.     

真菌曲霉F77对水中Cs~+的吸附

微生物在环境放射性污染修复中具有广泛的应用前景。从放射性污染土壤中筛选出一株耐辐射真菌曲霉F77,研究了它对水中Cs+的吸附及其影响因素。结果表明:酸对Cs+在曲霉F77上的吸附存在竞争作用,pH=2.0~3.5溶液中的Cs+几乎不被曲霉F77吸附;曲霉F77生长过程中代谢产生大量的酸性物质;Cs+的吸附随着曲霉F77培养时间的增长而增大,在曲霉F77逐渐衰亡时吸附降低;K+质量浓度小于500mg/L时对Cs+在曲霉F77上的吸附没有影响,当K+质量浓度大于500mg/L时Cs+的吸附随K+浓度增大而减少;溶液中Cs+质量浓度为0~500mg/L范围内,曲霉F77对Cs+均有较高的吸附,Cs+质量浓度为500mg/L时,Cs+的吸附量为27.6mg/g。温度影响曲霉F77对Cs+吸附的快慢,不影响最后的吸附量;曲霉F77对Cs+具有较好的吸附性能,表明曲霉F77具有吸附剂的潜质。     

裂片核素在岩石中的迁移研究Ⅵ.137Cs在花岗岩中渗透迁移及吸附动力学

用动态模型方程描述了裂片核素137Cs(实验中用134Cs模拟)随地下水流在花岗岩中的渗透迁移过程.由渗透曲线拟合求得模型参数--综合扩散-弥散系数和吸附速率常数,并在自行设计的水浴恒温槽中,进行了134Cs在花岗岩片上的吸附动力学研究.测定不同pH值和不同温度下的吸附曲线,推算出相应条件下的吸附速率常数及不同pH值时的吸附能.     

Sr在粉质粘土上的吸附比研究

采用静态批示法研究了接触时间、固液比、示踪液浓度及PH值对锶在粉质粘土上吸附比的影响.结果表明,Sr在粉质粘土上约7天达到吸附平衡,平均吸附比为20 mL/g; Sr的吸附吸附比随粘土粒度、固液比和初始浓度的增大而减小;随pH增大而增大;粉质粘土对锶的吸附能力很强,粘土是核废物处置的很好的备选回填材料.     

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.     

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.     

Gamma radiation levels in the ambient environment of the QNPP Base

Monitoring results of gamma dose rate level in 1992～2004 in the ambient environment of the Qinshan Nuclear Power Plants(QNPP)Base,the northeast of Zhejiang Province,are reported in this paper.It is shown that the gamma dose rate of five monitoring sites of 2.5 km to QNPP Base is 84～113 nGy/h,with an average of 96 nGy/h in the 13 years.The average value is close to the background level of 93 nGy/h prior to operation of the QNPP Base,and is lower than the monitoring result of 101 nGy/h at the reference site in Hangzhou City.Within 50 km from the QNPP Base,the cumulative dose rate of the thermoluminescent dosimeter(TLD)is 90 nGy/h,which is lower than the back- ground level of 111 nGy/h.