动态法-多接收电感耦合等离子体质谱测量痕量钚同位素丰度

^239Pu和^240Pu的相对含量与钚的级别及其来源密切相关。由于环境样品中钚的含量一般低至皮克甚至亚皮克量级，MC—ICP—MS测量^240Pu和^239Pu时需选用离子计数器来接收钚的束流。离子计数器之间的效率差异和质谱仪器固有的质量偏倚是影响准确分析钚同位素丰度比的两个主要因素。由于缺乏^240Pu／^239Pu的同位素标准物质，只能采用现有的^242Pu/^239Pu同位素标准来保持数据的溯源性。     

SUP>242/SUP>Pu同位素稀释剂的

首先用238Pu同位素稀释法标定了四水硫酸钚中239Pu的比活度,再用该239Pu溶液作稀释剂,对242Pu稀释剂进行标定,得到242Pu的比活度平均值为1 304 Bq/g,相对合成标准不确定度为1.4%.钚的同位素丰度比(R(239Pu/242Pu))为0.002 26,相对合成标准不确定度为4%;R(240Pu/242Pu)为0.017 2,相对合成标准不确定度为1%.     

山西、河南三地土壤样品中239+240Pu、137Cs分析

采用电感耦合等离子体质谱(ICP-MS)分析了中国中部地区三地(山西长治、河南濮阳和商丘)钻芯(0～30 cm)土壤样品中的239 240 Pu活度浓度和240Pu/239pu同位素比值,并对239 240 Pu和137Cs在土壤中的深度分布进行了研究.结果表明,三地表层土壤(0～2 cm)中239+ 240pu活度浓度为0.078 ～0.122mBq/g,137Cs为1.56 ～2.91 mBq/g,且浓度整体随深度增加而降低;240Pu/239 Pu原子比的平均值为0.188±0.016(全球沉降平均值为0.180±0.014),137Cs/239240Pu活度比值为34.61 ±5.91(1998年7月,全球沉降平均值为34±4).三地土壤中放射性核素137 Cs、239+240Pu浓度及钚同位素比值均与全球沉降值相当,说明其来源可能属于全球沉降.     

热表面电离质谱法测定钚氧化物中的钚同位素组成

采用热表面电离质谱法对钚氧化物中钚同位素丰度进行了测定。通过对钚氧化物样品预处理、离子源和分析器的真空控制、法拉第杯接收效率检测、测量过程中的信号强度大小控制、信号强度稳定性控制以及测量时间的控制等条件进行优化,确定了最佳预处理条件和测量条件,实现了钚氧化物中钚同位素组分的准确测定。在选定的条件下,测定了钚标准样品中的钚同位素丰度,主同位素239Pu和242Pu测量精密度(sr)均优于0.05%(n=6)。     

TIMS测定模拟1AF料液中铀钚同位素组分

采用溶剂萃取/离子交换分离-热表面电离质谱法,对模拟1AF料液中铀钚同位素组分测定技术进行了研究。通过对化学分离条件、仪器测量参数、信号强度、各种干扰等测定条件的研究和选择,实现了铀、钚同位素组分的精密测定。在选定的条件下,测定了模拟1AF料液中的铀钚同位素,主要同位素235U和239Pu测定精密度(sr)均优于0.05%。     

Reillex-Reillex阴离子交换分离克量级铀中微量钚北大核心CSCD

采用Reillex-Reillex串联阴离子交换色层柱,建立了高铀钚比样品中微量钚的高效分离方法。考察了树脂类型、淋洗条件、价态调节等对钚分离效果的影响,确定了分离流程的条件。当铀钚质量比为106时,经两级Reillex柱分离后,钚的平均回收率为99.35%,铀的去污因子大于107。最后使用该方法从克量级辐照铀靶中分离出了微克量级超纯239 Pu,(^(238)U+^(238)Pu)/^(239)Pu原子比为(3.60±1.15)×10^(-5)(n=6)。     

用AMS法测量新疆和湖北两地土壤样品中的钚

采用加速器质谱(Accelerator Mass Spectrometry,AMS)方法测量了我国新疆维吾尔自治区(罗布泊附近)和湖北省(襄樊和荆门)两地不同深度土壤样品中钚的比活度(239+240Pu)和240Pu/239Pu同位素比。测量结果显示:新疆表层土壤239+240Pu比活度为0.010～0.827mBq/g,240Pu/239Pu比值范围为0.155～0.214。新疆罗布泊附近两处钻芯土壤采样点的239+240Pu沉积通量分别为16.7Bq/m2和55.4Bq/m2。新疆土壤中钚比活度随土壤深度的分布呈现出两种模式:①比活度峰值出现在土壤表层以下,之后随深度呈指数方式衰减;②比活度从表层开始指数方式衰减。湖北省两处钻芯土壤采样所得土壤中239+240Pu沉积通量分别为44.9Bq/m2和54.6Bq/m2,239+240Pu比活度峰值在2～4cm和4～6cm出现,大小分别为0.418mBq/g和0.502mBq/g。两处土壤中240Pu/239Pu比值分别在0.170～0.210和0.186～0.220范围内。两地结果显示我国陆地土壤中240Pu/239Pu同位素比值均与全球沉降结果吻合。     

同位素稀释．萃取液闪法测量高放废液中的241Pu

在钚的238Pu、239Pu、240Pu、241Pu和242Pu5个同位素中,只有241Pu是β放射性核素,其余4个均为α衰变核素。241Pu的半衰期为14．29a,是钚同位素中放射性活度的主要贡献者,但能量很低（20．81keV）,直接测量它的β放射性是较为困难的,对复杂体系来说尤其如此。     

同位素稀释一多接收电感耦合等离子体质谱测量痕量钚年龄的方法研究

对钚材料的来源及历史的鉴定在许多领域是非常重要的。年龄是在追溯核材料的历史时第一个需要被测定的参数。钚样品的年龄测定基于钚的同位素及其子体，即238Pu／234U、239Pu/235U、240Pu/236U和241Pu／241Am的原子比的测定。     

伤口中钚监测装置

本文介绍了一台伤口钚监测装置,其探测元件为薄 NaI(Tl),用简易的铅帽屏蔽时,对~(239)Pu 的最小可探测量为0.1毫微居里。为了得到最大的优质因子,我们在选择探测元件尺寸及降低装置本底方面作了较仔细的研究,并推算出了晶体的最佳直径公式。对如何确定伤口中钚的含量,本文作了较详细的分析。针对钚在伤口中的深度及分布、钚的其它同位素的存在和非钚元素的污染对定量分析所造成的影响,提出了一些处理办法,并用实验结果与理论计算值作了比较。     

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.     

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.     

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.