利用模拟放射性焚烧灰合成钙钛锆石和榍石的研究

本文采用模拟放射性焚烧灰、天然锆英石为主要原料,通过配方设计,借助于失重-差式扫描量热(TG-DSC)、X射线衍射(XRD)等分析手段,研究钙钛锆石和榍石的高温固相反应合成.结果表明,采用高温固相反应,能够在较低温度获得高纯度的钙钛锆石和榍石;合成钙钛锆石和榍石的最佳温度及最低温度与配方有关,最低合成温度可低于1140℃.当焚烧灰掺量为0、20%、40%、60%时,配方的最佳合成温度分别为1260℃、1260℃、1230℃、1200℃.     

一种高放射性废物固化处理基材的制备方法

一种高放射性废物固化处理基材的制备方法，其特征包括：1）配料。以天然锆英石、CaCO2和TiO2为原料，按天然锆英石26-32重量份、CaCO2 29～35重量份、TiO2 35～42重量份的比例取各原料；2）细磨。将各原料装入细磨设备内，添加磨球后，振磨30-60min；3）煅烧。将物料在1150～1350℃的温度下煅烧20～60min，即制得产物。采用本发明制备钙钛锆石和榍石的人造岩石固化体，原料成本低廉，工艺简单（可以减少或避免固化处理过程中的二次污染），反应温度较低、得到的目标矿物纯度高，为钙钛锆石、榍石基人造岩石固化高放废物的工程化应用奠定了良好的基础。     

一种高放射性废物固化处理基材的制备方法

一种高放射性废物固化处理基材的制备方法，其特征是包括下列步骤：（1）配料：按质量比（26～32）；（29～35）：（35～42）取天然锆英石、CaCO3、TiO2原料；（2）细磨：将各原料装入细磨设备内，添加磨球后，振磨30-60rain；（3）煅烧：将物料在1150～1350℃下煅烧20～60min，即制得产物。采用本发明制备钙钛锆石和榍石的人造岩石固化体，原料成本低廉，工艺简单（可以减少或避免固化处理过程中的二次污染），反应温度较低，得到的目标矿物纯度高，为钙钛锆石、榍石基人造岩石固化高放废物的工程化应用奠定了良好的基础。     

掺钕钙钛锆石、榍石组合矿物固化体的浸出性能

以硅酸锆(ZrSiO4)、碳酸钙(CaCO3)、二氧化钛(TiO2)、氧化铝(Al2O3)和氧化钕(Nd2O3)为原料,采用固相反应工艺,制备掺钕钙钛锆石、榍石组合矿物固化体,借助X射线衍射(XRD)、背散射二次电子像(BSE)、荧光光谱(FS)、能谱(EDS)等分析手段,研究掺钕钙钛锆石、榍石组合矿物固化体的化学稳定性。结果表明,钙钛锆石、榍石的组合矿物能很好地固溶Nd,固化体具有良好的化学稳定性;在90℃,第42d,CZ15-1260、CZA15-1260、CA15-1260固化体样品的平均归一化浸出率分别为1.82×10-4、1.38×10-4、1.48×10-4g·m-2·d-1;固化体的较佳烧结温度为1260℃。     

模拟放射性焚烧灰陶瓷固化的初步研究

以天然锆英石、模拟放射性焚烧灰为原料,对模拟放射性焚烧灰的陶瓷固化进行了初步研究.借助X射线衍射(XRD)、扫描电镜(SEM)、密度分析等分析测试方法,研究了陶瓷固化体烧结温度和物相组成.结果表明,随着模拟放射性焚烧灰掺量的增加,ZrSiO4的分解温度降低.陶瓷固化体的主要晶相及其烧结温度与模拟放射性焚烧灰的掺量有关,当模拟放射性焚烧灰掺量为20%时,固化体的较佳烧结温度范围是1 230～1 290℃,主要晶相为ZrSiO4;当掺量40%时,固化体的较佳烧结温度范围是1 200～1 260℃,主要晶相为ZrSiO4和ZrO2;当掺量60%时,固化体的较佳烧结温度范围是1 290～1 350℃,主要晶相为ZrO2.     

掺铀榍石人造岩石固化体的制备及其浸出性能

以碳酸钙(CaCO3)、二氧化钛(TiO2)、氧化铝(Al2O3)、氧化硅(SiO2)和硝酸铀酰(UO(2NO3)2.6H2O)为原料,采用固相反应工艺,制备掺铀榍石基人造岩石固化体。借助X射线衍射(XRD)、扫描电子显微镜(SEM)等分析手段,研究固化体的烧结温度、物相组成、U元素的浸出性能等。结果表明,掺铀榍石基人造岩石固化体的较佳烧结温度是1 260℃;榍石能很好地固溶U形成榍石固溶体;配方化学式为Ca095U0.05Ti0.9Al0.1SiO5、Ca092U0.04Ti0.9SiO5固化体,28天90℃的浸出率分别为7.0×10-10m.d-1、9.5×10-10m.d-1,其归一化浸出率分别是2.10×10-3g.m-2.d-1、1.76×10-3g.m-.2d-1。     

人造岩石固化掺铀模拟放射性焚烧灰

以天然锆英石、模拟放射性焚烧灰、CaCO₃、TiO₂、UO₂为原料,采用高温固相反应,对人造岩石固化掺铀模拟放射性焚烧灰进行研究。借助XRD、SEM、抗浸出性能测试等分析测试方法,研究固化体的性能。结果表明：在空气气氛下烧结,固化体的晶相为CaZrTi₂O₇［Ca（Zr,U）Ti₂O₇］、CaTiSiO₅、CaTiO₃和CaUO₄,一部分U固溶于Ca（Zr,U）Ti₂O₇中;较多CaZrTi₂O₇的生成有利于Ca（Zr,U）Ti₂O₇固溶更多的U;模拟放射性焚烧灰掺量为60%、UO₂含量为6.88%的人造岩石固化体,1～35d铀的归一化浸出率为0.17~2.81μg/(cm²•d),42～192d铀的归一化浸出率为0.09～0.13μg/(cm²•d)。     

钕在钙钛锆石和榍石组合矿物中的固溶机制

以ZrSi O4、CaCO3、Ti O2、Al2O3、Nd2O3为原料,引入Al3+作价态补偿,通过固相反应制备包容模拟三价锕系核素Nd的钙钛锆石(CaZrTi2O7)和榍石(CaTiSi O5)组合矿物固化体。利用X射线衍射(XRD)、扫描电镜/能谱仪(SEM/EDS)研究其矿相组成、微观结构和元素分布,探讨Nd在钙钛锆石和榍石组合矿物固化体中的固溶机制。研究表明:钙钛锆石和榍石组合矿物固化体较佳的合成条件是在1 230℃条件下保温30 min,较佳配方的摩尔比为n(Ca1-x/2-y/4Nd(x+y)/2Zr1-y/4Alx/2Ti2-x/2O7)∶n(Ca1-xNdxAlxTi1-xSi O5)=[4/(4-y)]∶1;Nd3+能够进入钙钛锆石和榍石晶格,榍石能够固溶Zr4+、Al3+、Nd3+,Zr4+和Nd3+取代Ca2+位,Al3+占据Ti4+位,钙钛锆石能够固溶Al3+、Nd3+,Nd3+进入Ca2+位和Zr4+位,Al3+占据Ti4+位。     

富烧绿石型人造岩石固化模拟锕系元素废液的研究

采用与钙钛锆石（Ｚｉｒｃｏｎｏｌｉｔｅ）性能相近的烧绿石（Ｐｙｒｏｃｈｌｏｒｅ）为主要矿相，制备了对锕系元素废液有不同包容量（３７％～５０％）的人造岩石固化体，测定了其物理性能。应用Ｘ射线衍射（ＸＲＤ）、扫描电镜能谱分析（ＳＥＭ／ＥＤＳ）研究了其太相组成、微观结构和相组分分析，并采用产品一致性测试（ＰＣＴ）粉末浸泡法研究其抗浸出性能。研究结果表明，富烧绿石人造岩石是固化锕系元素废液并最终进行地质处     

锕系核素的人造岩石固化

介绍了锕系核素人造岩石固化的基本原理，概述了钙钛锆石的晶体结构和主要性质以及锕系核素和稀土类似物在其中的固溶情况，讨论了富钙钛锆石型人造岩石固化锕系核素的配方设计。表明用此方法包容高放废液中锕系核素具有良好的前景。     

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.