分子活化分析法研究地质样品中铂族元素的化学种态

用化学逐级溶解、镍流火试金项富集及中子活化分析法研究了中国东部大陆地幔橄榄岩捕掳体中铂族元素的化学种态。分析结果表明，6个物相中单个铂族元素的质量分数加和与铂话元素总量分析结果基本相符；硫化物相中铂话元素分布特征的研究，进一步说明了硫化物的熔出是部分熔融过程中地幔橄榄岩铂族元素分异的重要机制之一。     

地质样品中痕量铑的火试金预富集中子活化分析

简述了铅试金和镍锍试金富集地质样品中痕量铑的分离方法,并结合中子活化分析测量了5种地质标准物质中铑的含量。铅试金法的流程回收率（n=4）为81.5%±1.2%;镍锍试金法的流程回收率（n=6）为75.1%±3.9%,对简单化学标准和地质标准物质基体,铑的回收率相近。对5种地质标准物质中铑含量的分析结果与标准值在不确定度范围内一致。铅试金中子活化法可实现10^－9铑含量的准确测量,镍锍试金中子活化法可实现10^－10铑含量的准确测量。对两种富集方法中的干扰因素进行了讨论,并对铅的自吸收效应进行了修正。探测极限的计算结果表明：镍锍试金预富集并用平面锗探测器测量,可获得更好的分析灵敏度。     

铜镍矿样中铂和钯的离子交换预富集中子活化分析研究

在铂族元素中子活化分析中，应用溶剂萃取和磺酸型阳离子交换树脂相结合的方法，分离富集铜镍矿样中铂、钯的化学前处理流程，并对与该流程结合的中子活化方法进行了概述。各项相关参数均表明该方法可用于铜镍矿样中的铂钯分析。     

利用252Cf源对镍精矿进行中子活化分析

利用MCNP模拟改进了中子活化分析的装置，并采用中子产额较高的^252Cf作中子源，对镍精矿样品和标准样品进行照射；利用相对测量法对用高纯锗探测器得到的镍精矿和标准样品的活化能谱进行能谱处理，得到镍精矿的元素成分和含量。结果显示，^252Cf中子源中子活化在线分析可以较好地满足工业要求。     

^154Sm（n,2n）^153Sm和^148Sm（n,p）^148gPm反应测面的测量

报道了在Ｅｎ＝１４．５－１４．９ＭｅＶ中子能区用活化法以＾２７Ａｌ（ｎ，ａ）＾１４Ｎａ的反应截面为中子注量标准测得的＾１５４Ｓｍ（ｎ，２ｎ）＾１５３Ｓｍ和＾１４８Ｓｍ（ｎ，ｐ）＾１４８ｇＰｍ反应截面，并将其与已有的数据进行了比较，中子能量用铌锆截面比法测定。     

^152Sm的22—1019keV能区中子俘获截面的测量

在４．５ＭｅＶ静电加速器上，利用＾７Ｌｉ（ｐ，ｎ）＾７Ｂｅ和Ｔ（ｐ，ｎ）＾３Ｈｅ反应作为中子源，在２２－１０１９ｋｅＶ中子能区以＾１９７Ａｕ的中子俘获截面为标准，用活化法测量了＾１５２Ｓｍ的中子俘获截面，其误差小于６．８％。     

5.0MeV和9.5MeV快中子辐照在GaAs中产生的辐射损伤的正电子湮没研究

采用正电子湮没寿命测量方法研究了５．０ＭｅＶ和９．５ＭｅＶ快中子辐照在ＧａＡｓ中产生的辐射损伤，实验结果表明１０＾１１－１０＾１２ｎ／ｃｍ＾２注量的中子辐照只产生单空位缺陷１０＾１３ｎ／ｃｍ＾３注量的中子辐照产生单空位和双空位缺陷，１０＾１２ｎ／ｃｍ＾２注量的９．５ＭｅＶ中子辐照的ＧａＡｓ经４５０－６２０℃退火产生三空位缺陷，产生的缺陷浓度随中子能量和注量的增大而增大，但缺陷产生率对中子注量更灵敏     

峰面积比法测量绝对热中子注量率

介绍了利用γ谱仪测量绝对中子注量率的方法。在已知中子场中照射金（Ａｕ）箔和铕（Ｅｕ）箔，利用γ谱仪分别测量＾１９８Ａｕ和＾１５２Ｅｕ的４１１ｋｅＶγ峰面积，根据两者的峰面积之比和已知中子场的约对中子注量率，求得＾１５２Ｅｕ的４１１ｋｅＶγ峰面积对应的中子注量率。在待测中子场中，照射金箔，利用γ谱仪测量其４１１ｋｅＶγ峰面积和刻度过的＾１５２Ｅｕ的４１１ｋｅＶγ峰面积，根据两者之比和已求得的＾１５２     

中能重离子与^natW相互作用中Hf的同位素分布

用放射化学方法测量了４０ＭｅＶ／ｕ＾４０Ａｒ，１０＼６５ＭｅＶ／ｕ＾８４Ｋｒ，８０ＭｅＶ／ｕ＾１６Ｏ，１３５ＭｅＶ／ｕ＾１２Ｃ＋＾ｎａｔＷ反应中Ｈｆ的生成截面，得到了Ｈｆ的同位素分布。研究表明，利用ＨＩＲＦＬ能量的重离子和丰中子重靶作用，能以一定的截面生成Ａ＞１７０区丰中子新核素，Ｎ／Ｚ值高的炮弹有利于丰中子核素的生成，过高的炮弹能量对丰中子新核素的生成没有贡献。     

新丰中子核^1^8^5Hf—^1^8^5Ta的递次变曲线分析

本文报道一个分析递次变曲线的优化方法和计算机程序。通过对旨在首次合成新丰中子核＾１＾８＾５Ｈｆ的实验数据的分析，得到了＾１＾８＾５Ｈｆ的半衰期。分析结果检验和支持了新丰中子核＾１＾８＾５Ｈｆ的合成和鉴别结论。     

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.