几种水泥固化体中HTO浸出性研究

进行了HTO在沥青涂覆水泥固化体，苯乙烯单体聚合物浸渍水泥固化体和裸体水泥固化体中的长期浸出实验，给出了三种固化体的物理性能及长期浸出实验数据，结果表明，沥青涂覆，苯乙烯单体聚合物浸渍水泥固化体的物理性能比裸体水泥固化体有了较大程度的改善，其HTO浸出率和累积浸出分数都明显地优于裸体水泥固化体，累计浸出372d后，苯乙烯单体聚合物浸渍水泥固化体样品的浸出率和累积浸出分数均比裸体固化体样品的相应参数降低了2个数量级，苯乙烯单体聚合物浸渍水泥固化体的扩散系数De比裸体水泥固化体降低了3个数量级，说明聚合物浸渍固化体对固化体中氚的固定是非常有效的。     

用聚合物浸渍氚化混凝土固化含氚废水

本文介绍了固化含氚废水的聚合物浸渍氚化混凝±(PITC)方法。还报道了 PITC 固化体浸出试验和抗压强度的结果。试验结果表明,PITC 可使固化体的氚累积浸出分数较普通水泥固化体降低1—2个数量级。     

含氚废水水泥固化的工艺及设备

本文介绍了本院水泥固化含氚废水的工艺概况和主要设备，并给出了含氚废水水泥浆和固化体性能及浸出实验结果。实验结果表明，沥青涂覆固化体表面和金属密封容器相结合处理含氚废水是实际可行的。     

非饱和浸出实验中水泥固化体体积对137Cs浸出性能的影响

本文介绍了非饱和浸出实验中水泥固化体试块体积大小对137Cs浸出影响的一些结果,包括累积浸出份额Ft、浸出通量分数Jn和等效扩散系数De等.实验用浸出介质为石英砂;石英砂中水的饱和度在39.4%～100%之间,共计5个饱和度;被浸固化体的体积在40.2 cm3～16945.5 cm3之间,共计8种规格.结果表明,Ft随着固化体试块体积V的增大而减小,并可以用Ft=a×Vb很好地拟合;Jn随固化体试块体积V的增大而明显降低,而且可以用Jn=c×Vd很好地拟合;De不是常数,而是随固化体试块体积V的增加而增大.由此可以看出,浸出实验不考虑固化体试块体积的大小以及浸出时间的影响,将会得出与实际处置释放源项相差甚大的结果.     

模拟放射性含氟废液水泥固化配方的研究

本文以沸石、硅灰、石英砂为添加剂,按照质量比m（沸石）∶m(硅灰)∶m（石英砂）∶m（水泥）=1∶1∶3∶10配方对模拟放射性含氟废液进行水泥固化。由配方得到的水泥浆流动度和初、终凝时间满足桶内固化要求。测定了水泥固化体28 d的抗压强度、抗浸泡性和抗冻融性实验后的强度损失,进行了抗冲击性能测试和模拟核素浸出实验。结果表明,该配方可有效地固化模拟放射性含氟废液,固化体28 d抗压强度、各项实验强度损失和模拟核素浸出率均满足GB 14569.1-2011的要求。水泥固化体的F^-浸出率很低,XRD显示F^-以CaF₂形式存在。废液中F^-质量分数控制在1%较为合适,此时水泥固化体终凝时间为14 h,F^-的42 d浸出率为2.54×10^-3 cm/d。     

高放废液碱矿渣水泥固化体研究

介绍了用碱矿渣水泥固化高放废液新工艺。该工艺以碱矿渣水泥为基体,掺加适量沸石和硅灰,无需加温加压,利用静态爆破剂水化时产生的膨胀压,在限容下使水泥基体致密。其抗压强度、耐热性和浸出率等性能均优于其它水泥。当废物氧化物包容量为25％时,固化体抗压强度可达65～100MPa,孔隙率可小于10％,Cs和Sr的浸出率可分别达到10~(-5)g·cm~(-2)·d~(-1)与10~(-7)g·cm~(-2)·d~(-1)水平。高放废液碱矿渣水泥固化体与玻璃固化体性能相当;而固化工艺比玻璃法简单。此外,还探讨了固化机理,核素离子在碱矿渣水泥固化体中的形态。     

硅酸盐水泥基材中钙硅比对铀(Ⅵ) 滞留性能的影响

以氧化钙、硅灰为原料，在80℃水热条件下，能合成不同钙硅比的水化硅酸钙(CSH)，用X射线粉晶衍射(XRD)鉴定表明产物都为凝胶相。对含铀的不同钙硅比的CSH凝胶，用1％的盐酸溶液浸出，结果表明：低钙硅比的CSH凝胶对铀有更好的滞留性能。在25℃条件下，含铀普通硅酸盐水泥和碱矿渣水泥固化体102天的浸出结果表明：碱矿渣水泥固化体中铀的累积浸出分数和扩散系数分别比普通硅酸盐水泥固化体中低17．6％和40．6％，这与碱矿渣水泥中钙硅比低有关。     

搅拌参数对放射性废液水泥固化体性能的影响

目前,国内核电站或核设施产生的中低放废液都采用水泥固化进行处理,水泥浆及水泥固化体性能是水泥固化技术重点研究内容。本文采用普通硅酸盐水泥固化中低放废液模拟料液,研究不同液灰比条件下,搅拌时间和搅拌速度对水泥浆流动度和固化体28 d抗压强度、孔结构、显微结构和抗浸出性能的影响。结果表明：在相同液灰比下,随着搅拌时间的延长（10～50 min）,水泥浆的流动度和固化体抗压强度呈现先增大后减小的趋势,而固化体的孔隙率和Sr²⁺浸出率随搅拌时间的延长呈递减的趋势,搅拌50 min的固化体的结构较搅拌10 min的固化体致密;用较大搅拌速度制备的固化体的抗压强度较高,且在搅拌30 min内,提高搅拌速度可提高浆料的流动度;然而长时间用较大速度搅拌制备的固化体的孔隙率较高,同时核素浸出率也较大。由于固化工艺过程中搅拌速度和搅拌时间会影响水泥浆的流动性和固化体性能,因此在水泥固化装置投入使用前,应通过大量实验来确定满足工艺要求且满足固化体性能的最佳搅拌参数。     

放射性废离子交换树脂特种水泥固化体的微观结构分析

研究了特种水泥 (ASC)树脂固化体的微观结构。用压汞实验比较了ASC特种水泥的树脂固化体和普通硅酸盐水泥 (OPC)固化体多孔性能 ,通过电镜扫描 (SEM )观察比较了ASC和OPC的微观晶体结构。分析结果发现ASC水泥固化体具有较好的孔形结构 ,这是ASC固化体浸出率低的原因 ;ASC水泥固化体晶体呈针状结构 ,OPC水泥固化体晶体呈片状结构 ,针状结构的力学性能和结构强度要比OPC的片状结构好 ,该结构是ASC固化放射性废树脂包容量大、强度高的根本原因。     

非饱和浸出实验后水泥固化体内137Cs分布特征

非饱和浸出实验完成后,经分层分段切削取样测量,得到了被浸水泥固化体试块内剩余137Cs的比活度分布.结果表明,固化体内137Cs比活度A(d,h,t)随径向距离d的增加而减少;沿径向的分布可以用公式A/A0=1-a×exp[-b×(R-d)]很好地描述,公式中A0为试块内137Cs的初始平均比活度,R为固化体试块的半径,d为固化体的径向坐标,t为浸出实验的时间,a、b为拟合系数,它们与固化体周围浸出介质中水的饱和度S和浸出实验持续时间t密切相关.以浸出前后核素比活度变化小于5%的深度d max为最大浸出深度,在本实验的各种条件下,d max约为2.25 cm.另外,核素的轴向分布呈现中间较高、两端较低的现象,说明在固化体两端分布的137Cs,除了沿径向浸出外,还沿轴向浸出.     

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.