模拟高放废物地质处置条件下锝在去离子水体系中的胶体行为

⁹⁹Tc是高放废物地质处置中重点关注的关键核素,深地质处置条件下其在地下水中的胶体行为对其迁移行为可能存在较大影响,亟需系统开展研究。本文在模拟高放废物地质处置的低氧和低浓(氧气含量小于5 ppm、⁹⁹Tc初始浓度10^-9～10^-5 mol/L)条件下,首先探讨了用膜过滤法研究锝胶体行为的可行性,发现pH值和离子强度等对⁹⁹Tc的液闪测定无明显影响,且过滤器对Tc(Ⅳ)和Tc(Ⅶ)均无显著吸附行为,基于此初步建立了锝胶体行为研究的膜过滤实验方法,并采用该方法研究了去离子水体系中锝的胶体行为。结果表明：Tc(Ⅶ)不易发生水解反应,在低氧条件下无明显胶体行为,并能长期稳定地存在于体系中,可能具有较强的迁移能力;Tc(Ⅳ)易水解而聚集为胶体,在较宽pH值范围内(pH=4～11)以真胶体形式在398 d实验周期内较长期地稳定存在于体系中,其浓度高于以离子形态存在的Tc(Ⅳ)的数倍甚至1个数量级,所形成的胶体可能会提高地质处置条件下Tc(Ⅳ)的迁移能力,但体系离子强度升高会使Tc(Ⅳ)胶...     

Purex流程铀钚分离工艺中锝对镎走向的影响

在HNO3-U(Ⅳ)-N2H4-Tc(Ⅶ)-Np(Ⅴ)体系中,Np(Ⅴ)迅速还原为Np(Ⅳ)。对比研究表明,Tc是该体系中Np(Ⅴ)迅速还原的主要原因。该体系中的主要反应是U(Ⅳ)将Tc(Ⅶ)还原为Tc(Ⅳ),进而Tc(Ⅳ)将Np(Ⅴ)还原为Np(Ⅳ)。本文通过串级和台架实验研究了该体系中锝对镎走向的影响。结果表明,Np(Ⅴ)的还原速度随HNO3浓度、初始Tc浓度的增大和温度的升高而加快。在模拟Purex流程铀钚分离工艺的条件下,试管串级和微型混合澄清槽台架实验结果表明,提高1AP料液中Tc(Ⅶ)的浓度、升高反应温度,Np进入1BU中的百分含量增加。     

痕量单一价态钚溶液的制备

建立了痕量Pu(Ⅳ)、Pu(Ⅴ)、Pu(Ⅵ)溶液的制备方法,并跟踪了各价态钚溶液的稳定性。采用TTA选择性萃取Pu(Ⅳ)、HDEHP萃取Pu(Ⅳ+Ⅵ)的方法分析了溶液中钚价态的分布。结果表明,将浓度为10-11 mol/L量级的钚溶液在1mol/L HNO3体系中反复蒸干可制得Pu(Ⅳ)溶液;Pu(Ⅳ)在0.5~1mol/L HNO3-0.1mmol/L KMnO4溶液体系中反应24h,可获得Pu(Ⅵ)溶液;Pu(Ⅵ)避光保存5d后,可得到Pu(Ⅴ)溶液,各单一价态钚溶液的纯度均大于90%。在pH=3.0、0.01mol/L NaCl体系中,各价态均不能稳定存在,因此,所需单一价态钚溶液应新鲜制备。     

硝酸体系中Tc(Ⅶ)与乙异羟肟酸的反应动力学研究

采用溶剂萃取法研究了HNO₃溶液中乙异羟肟酸（AHA）与Tc(Ⅶ)的相互作用。结果表明,有AHA存在时,Tc在30%TBP/煤油HNO₃体系中的分配比随反应时间下降,在实验条件下反应50 h后Tc在两相中的分配基本达到平衡,分配比D_Tc降至0.03,这表明Tc(Ⅶ)能被AHA还原为亲水性的低价Tc配合物［Tc^Ⅱ(NO)(AHA)₂H₂O］⁺;溶液吸收光谱显示,反应产物在428 nm（ε＝2 559 L·mol^-1·cm^-1）和565 nm处有吸收峰。通过溶剂萃取法得到Tc(Ⅶ)还原反应的表观反应速率方程式为r＝-dc(Tc(Ⅶ))/dt＝k′c(Tc(Ⅶ))c^1.6(AHA),在18 ℃下,c(AHA)＝1.0 mol/L,c(HNO₃)＝0.50 mol/L时半反应时间t_1/2＝16.5 h。进一步研究了溶液中有Pu(Ⅳ)存在时AHA与Tc(Ⅶ)的作用以及Tc分配比的变化。结果表明：Pu(Ⅳ)的存在会加快Tc(Ⅶ)转化为低价态亲水性配合物,而Pu的分配比在过程中基本不变。     

99Tc在Fe,Fe2O3和Fe3O4上的吸附行为研究

用批式法研究了大气条件下99Tc在Fe,Fe2O3和Fe3O4上的吸附行为,考察了吸附平衡后溶液中99Tc的存在价态.实验结果表明随着溶液pH值(5～12)、CO2-3浓度(1×10-8～1×10-2 mol/L)的增大,99Tc在Fe上的吸附比减小;溶液pH值、CO2-3浓度的变化基本不影响99Tc在Fe2O3和Fe3O4上的吸附;99Tc在这3种吸附材料上的吸附行为均可用Freundlich吸附等温式表示;当Fe作吸附材料时,吸附平衡后99Tc主要以Tc(Ⅳ)的形式被吸附,当Fe2O3和Fe3O4作为吸附材料时,99Tc主要以Tc(Ⅶ)的形式被吸附.     

二氧化碳和腐殖酸对Np(Ⅳ)、Tc(Ⅳ)溶解度影响研究

正在高放地质处置的低氧条件下,Np(Ⅳ)、Tc(Ⅳ)等可能在地下水中发生水解反应,以溶解度很低的水解产物形式存在而不易迁移,但地下水中的二氧化碳和腐殖酸也可能与这些水解产物作用,生成溶解度较大的物质,使低价态的Np、Tc等也容易发生迁移。本研究在低氧(O_2浓度小于     

硅基阴离子交换剂吸附Tc(Ⅶ)

主要研究了硅基阴离子交换剂（以下简称SiR₄N）在硝酸溶液中对Tc(Ⅶ)的吸附行为及其影响因素。结果表明,在0.50mol/L HNO₃介质中,SiR₄N对Tc(Ⅶ)的吸附分配系数为370mL/g,吸附平衡时间为35min;机理研究表明,Tc(Ⅶ)主要以TcO^-₄阴离子的形式被SiR₄N吸附;SiR₄N对Tc(Ⅶ)的吸附等温线基本符合Langmuir吸附等温线,属单分子层吸附,吸附热为-18.48kJ/mol;在0.50mol/L HNO₃介质中SiR₄N对Tc(Ⅶ)的静态饱和吸附量为0.30mmol/g(干)。     

PUREX流程中锝对U(Ⅳ)-肼的稳定性影响

通过分光光度法研究了硝酸体系中锝催化硝酸氧化U(Ⅳ)-肼的反应,结果表明:温度和锝浓度是影响锝催化硝酸氧化U(Ⅳ)速率的主要因素,Tc催化硝酸氧化U(Ⅳ)反应对Tc的级数为1.23,反应活化能Ea=79.2kJ/mol,Tc催化硝酸氧化U(Ⅳ)反应对U(Ⅳ)的级数为0,平均速率常数为1.60×10-4 min-1。肼浓度对锝催化氧化U(Ⅳ)的速率影响较小,Tc-U(Ⅳ)-肼体系中肼的氧化和U(Ⅳ)的氧化同时进行,但U(Ⅳ)早于肼氧化完,随后肼快速氧化完全,与Tc-肼体系相比,肼的氧化速率略有降低,U(Ⅳ)对肼的氧化既有促进作用,又有抑制作用。Tc-U(Ⅳ)-Pu(Ⅲ)-肼体系中,当锝浓度为0.005 mol/L,Pu(Ⅲ)稳定存在的时间小于45min。     

Tc(Ⅳ)在地下水中的溶解度测定

本工作在低氧条件下,以SnCl2为还原剂,测定了Tc(Ⅳ)在我国高放废物地质处置预选场场址——甘肃北山3号井地下水中的溶解度,同时对溶解平衡后Tc的存在价态及可能的存在形态进行了探讨。实验结果表明:在实验条件范围内,溶液的pH值及Eh值对Tc的形态影响很大,即随着溶液pH值增大,Tc     

H_2O_2调价UTEVA树脂对钚的分离方法

研究了H2O2调节钚价态至Pu(Ⅳ)的条件,对于钚质量浓度在10-3 g/L量级的溶液,适量H2O2可以将钚价态稳定在Pu(Ⅳ)。采用粒径为50~100μm的UTEVA树脂填充的柱体积为2mL的萃取色层柱,在6mol/L HNO3浓度下,使用w=1.5%H2O2作为氧化还原剂对10-2 g/L的钚进行预处理,能将钚吸附上柱。通过适当条件的洗脱,在铀、镎、钚混合溶液中,得到钚的回收率约为108%。     

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.     

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.