多接收电感耦合等离子体质谱法对铀同位素丰度的测定

为了对环境监测提供有效、可靠的手段,在多接收电感耦合等离子体质谱(MC-ICP-MS)上建立了铀同位素丰度的分析方法。对影响仪器灵敏度的因素进行了初步探索,对标准物质GBW 04227和3个同位素丰度不同的样品中铀的各种同位素组分比值进行了测量,评价了测定结果的不确定度。结果表明,对丰度为3%、质量分数为2×10-7的235U溶液,R(235U/238U)丰度比的相对实验标准偏差优于0.02%,R(236U/238U)丰度比的相对实验标准偏差优于0.2%。     

同位素稀释质谱法测定高放废液中的铀

用双同位素稀释质谱法测定高放废液中的微量铀,采用TBP/Kel-F粉反相分配色层法分离铀,双稀释剂分别为浓缩~(235)U及~(238)U,铀同位素丰度比的质谱测定相对标准误差优于0.1%,化学处理及质谱测定全流程铀的空白值为3×10~(-9)g,方法检测限对于铀为1×10~(-9)g,高放废液中微量铀测定结果不确定度为±2%。     

堆后铀产品中232U测定方法研究

²³²U是燃料元件制造中需严格控制的铀同位素,为此,需建立一种准确的测量方法。本工作建立了一种α谱仪和质谱法相结合测定铀产品中²³²U含量的新方法。采用质谱法测量²³⁴U、²³⁵U、²³⁶U与²³⁸U的同位素丰度比,α谱仪测量²³²U的活度和²³⁴U、²³⁵U、²³⁶U、²³⁸U的总活度,即可计算出铀产品中²³²U的浓度。对于²³²U含量为1.118 ng/g的样品,16次测定数据的相对标准偏差为3.43%,证明该测量方法有效,可应用于实际样品的分析测定。     

研究动态

中国原子能科学研究院放射化学所同位素分离组在离子交换色谱法分离铀同位素的基础研究方面最近取得突破性进展。该研究组采用的一个分离体系,是使原料铀溶液在2.5h内通过约1m长的色层柱,在后沿界面上得到了丰度R=[~(235)U]/[~(238)U]=0.008180的浓缩样品,比料液(天然铀)丰度0.007280提高12％以上。日本在离子交换色谱法分离铀同位素这一     

容器内铀同位素丰度的非破坏探测技术研究

研制了三维样品旋转装置,用PC/FRAM软件分析了通过同轴HPGe探测器采集的铀总量在2—600g、能区在120—1001keV的铀同位素γ射线。建立了高放废物容器内非均匀分布的铀同位素丰度的γ能谱测量方法。对同位素丰度在20%—93%的235U,测量不确定度<0.6%,对238U的测量不确定度<1.3%。     

ISOCS在铀同位素丰度比测量中的应用

本文介绍了应用就地计数系统(ISOCS)测量235U和238U丰度比的方法。该方法使用基于蒙特卡罗原理的无源效率刻度软件对235U和238U子体234mPa进行效率刻度,采用平衡铀测定方法计算出235U和238U的原子比。使用该方法对某一铀样品进行了分析,其测量结果与质谱法测量结果的相对偏差为2.2%。     

AMS直接测量铀微粒次同位素比的方法

铀微粒同位素比测定在核保障环境取样中发挥着重要作用,目前铀微粒中次同位素比的准确测定方法尚未完善.本工作使用小型加速器质谱研究了一种直接测量铀微粒中次同位素比的分析方法,采用CRM铀系列同位素标准样品,选取不同丰度、不同粒径的铀微粒进行测量分析,CRM-U200、CRM-U970微粒234 U/235 U和234 U/...     

用内标技术测量环境样品中的铀

用MAT 262热表面电离型同位素质谱计测定了铀的同位素丰度比。环境样品采用HNO3 HF HClO4混合溶液溶解后,用TBP色层法进行分离纯化,再经电镀制备成供质谱用的测量源。结果表明,所测环境样品中铀的质量分数为:河水,8×10-8;长青树树叶,1×10-7;表层土壤,(5～11)×10-6。     

用中子活化分析法测定~(238)U/~(235)U同位素丰度比

本文论述了用中子活化分析法测定含微量铀的样品中~(238)U/~(235)U同位素丰度比的原理及方法。样品在反应堆中接受短时间照射后,用Ge(Li)探头或高纯锗探头-多道能谱分析仪-计算机系统测量射线的能谱.可以分辨出~(238)U和~(235)U的许多监测峰。利用这两种监测峰计数之比与这两种同位素丰度比成正比的关系,分析铀的同位素丰度比,在~(235)U丰度为0.6％-18％范围时精密度为1％-2％,在贫化铀和18％-60％丰度~(235)U时,精密度为2％-3％。     

加速器质谱法测量含铀微粒中铀同位素比的方法研究

准确测定含铀微粒同位素比在核保障中有重要的应用价值。本文采用将含铀微粒溶解并加入高纯Fe粉烘干的方法制样,采用中国原子能科学研究院的HI-13串列加速器质谱测量靶样中的同位素比。通过对CRM铀系列同位素标准样品的分析表明,该方法可测定高于10^-5的²³⁶U/²³⁸U同位素比;对于²³⁵U/²³⁸U同位素比在10^-4～10^-1范围内的含铀微粒,²³⁵U/²³⁸U同位素比相对扩展不确定度均小于10%。     

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.