用厚源α计数测定TL和ESR年代中的钍、铀年剂量

本文叙述了用厚源α计数技术测定TL和ESR年代中钍系和铀系年剂量的原理和方法。该方法主要优点是测定α年剂量时,可将计数率直接代入生龄公式,不需要计算钍、铀含量和剂量率转换因子。但在估算β和γ年剂量时,必须假定样品中的钍、铀放射性是相同的,或者用“对”技术来确定钍、铀含量。     

级联α-对法测定微量铀和钍

陶器和瓷器中所含铀和钍的量在大多数情况下是很少的,针对这一特点,选用级联α-对法测定微量铀和钍。方法的优点是简便易行,用无限厚源,制样比较简单;探测元件采用ZnS屏,加上一套测定α-粒子的装置,要求它能够区分总的α-计数和级联α-计数。     

土壤样品中总α测量刻度方法探讨

土壤样品中总α测量采用厚源法,仪器通过刻度后,对样品进行测量。通过对土壤样品成分的分析,选择两种刻度源——241Am源和编号为GBW04127的铀钍天然系矿石标准物质分别对低本底α、β测量仪进行刻度,用9个国家标准物质模拟土壤样品,通过数据对比可知:对于用混合源作为验证源来说,用GBW04127作为刻度源比用241Am测量结果更为准确,误差由20%~40%降至20%以内;对于其它标准样品,误差并没有得到改善,多数反而增大。因其成分组成与真实的土壤有较大差距,土壤中不单一含有U、Th或K成分,混合源与真实的土壤放射性成分更接近,更能代表土壤样品。因此,土壤样品中总α测量刻度源可以考虑使用编号为GBW04127的铀钍天然系矿石标准物质。     

分光光度法测定飞来峡水库水中的铀、钍

用Fe(OH)2共沉淀淡水样中的铀和钍,经硝酸溶解后,用^235N－环己烷萃取铀钍,在盐酸介质中分光光度法分别测定飞来峡水库水样铀、钍的含量。结果表明,铀、钍的回收率稳定在80％以上,方法稳定可靠;飞来峡水利枢纽建成后库区水体中铀、钍的含量维持在以前的水平。     

钍在轻水堆中利用的研究

对钍－２３２在轻水堆中利用进行了研究。考虑到现行轻水堆改型的方便，以秦山核电厂反应堆参数为基础，只改变堆芯燃料组分，在可裂变材料总量不变的条件下，对不同钍－２３２装量进行了多方案研究。结果表明，由于钍－２３２吸收中子后的主要转换产物是铀－２３３，它在热堆中的η值比铀－２３５和钚－２３９的高，因此在同样初始过剩反应性情况下，随着钍－２３２装量的增大，燃耗的加深，堆内易裂变材料总生成量也随之增大，转换比提高，从而使堆芯寿期延长，节省了核燃料。可见钍是一种有前途的能源资源。此外必须指出，在所研究的参数条件下以钍－铀重量比０．２５为佳。     

甲基膦酸二甲庚酯(P_(350))色层分离-α谱测量~(234)U/~(238)U和~(230)Th/~(232)Th的活度比

一、引言 放射性铀、钍同位素在环保领域、水文地质中判断找矿远景,考古中测定古生物的年代得到广泛应用。 对铀、钍与其他干扰元素分离以及铀、钍互相分离,一般方法较复杂,需对铀、钍进行多次纯化。本文采用大孔型树脂X-5(聚二乙烯苯)为支持体,用水溶性小、对铀、钍分离效果好的P_(350)为萃取色层的固定相。将分离后的铀、钍分别电沉积制备成无载体的α面源,用α谱仪测定~(234)U/~(238)U,~(230)Th/~(232)Th的同位素活度比值。 本分离体系对高铀低钍、高钍低铀以及铁含量高的样品,均能得到满意的结果。本方法测定下限水样为1—2μg/1,固体样为5μg/g。10μg以上的铀、钍测定误差为±5％。     

活性炭吸附剂用于大体积水中铀,钍浓集的方法研究

对ＩＲＰ—２活性炭吸附剂应用于水中铀、钍的浓集进行了条件试验和验证，提出了适用于环境水样中铀、钍的浓集方法。结合不同分析方法的需要，对浓集于吸附剂上的铀、钍给出了用硝酸和盐酸两种体系的解析方法。结果表明，对２０Ｌ水样中的铀和钍均可达到９０％以上的回收，可以用于环境水样中铀、钍的浓集。     

稀土铁矿尘中钍含量的测定

本文报道了一种稀土铁矿尘样品中钍含量的测定方法。用 CL-TBP 萃淋树脂和743阳离子交换树脂分离、纯化钍,电沉积制源,然后进行α谱测量。本方法的全程回收率为94.3±3.2%,对铀和其他α核素具有较好的分离效果,方法的精密度和准确度较好。用本方法测定了部分稀土铁矿尘样品中钍的含量。     

α铀系测年试样化学前处理方法适用性评价

针对不同铀含量、不同样品纯度的样品,综合离子交换树脂柱铀钍分离-电沉积法和萃取色谱树脂柱铀钍分离-微沉积膜法,建立了α铀系测年离子交换树脂柱铀钍分离-微沉积膜法化学前处理方法。实验结果表明:离子交换树脂柱铀钍分离-微沉积膜法既适用于铀含量较高、样品较纯、用量较少的样品,也适用于杂质较多、铀含量较低、用量多的不纯碳酸盐样品,在样品化学前处理过程中具有更好的适用性。     

离子交换——分光光度法测定磷酸盐岩中的铀和钍

本文发展了一种选择性的阴离子交换分离—分光光度法用于测定磷酸盐岩中的铀和钍。用硝酸分解大约0.2g的岩样,在2.5mol/L硝酸镁—0.1mol/L硝酸中,用阴离子交换法将样品溶液中的铀和钍吸附在Amberlite CG 400(NO_3~-)柱上,分别用6.6mol/L硝酸和0.1mol/L硝酸依次洗提铀和钍,用偶氮胂Ⅲ分光光度法分别测定铀、钍,并提供了NBS标准磷酸盐岩和其它矿样中铀和钍的测量结果。     

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.