铀矿勘探手册(英文版)

本书系1971年9月21日至10月2日在伦敦由北大西洋公约组织的高级研究学会召开的铀矿物勘探方法的学术论文汇编。共收集20篇论文(每篇论文均附有讨论纪要),目次如下:①铀矿勘探的现状②铀的供应与需求,③铀矿床形成的几种环境,④砂岩型铀矿床用的勘探标准,⑤铀矿勘探费用,⑥中子活化分析作为铀矿地球化学勘探的辅助工具,⑦地球化学技术在铀矿勘探中的应用,⑧在铀矿的水文地球化学勘探中的设计和解释标准,⑨铀矿勘探用的仪表技术,⑩铀矿勘探用的轻便设备,(11)用γ射线能谱术评价铀矿,(12)航空γ射线测量技术,(13)加拿大氡的勘探方法,(14)铀矿勘探和评价的钻孔测井     

某废弃铀矿区环境放射性污染现状调查

介绍了在我国某废弃铀矿区开展的环境放射性污染调查,对γ辐射空气吸收剂量率、固体样(含铀矿渣)、土壤、水、底泥和生物中放射性核素及空气中氡等根据国家标准方法进行监测分析,同时对铀矿区居民所受年辐射剂量影响进行了评估.调查结果表明,该区域的放射性污染治理工作刻不容缓.最后根据该铀矿区污染源的特点,提出合理的辐射防护和治理手...     

基于γ能谱特征峰测定铀矿石样品铀-镭平衡系数

在铀矿勘探中,了解铀系平衡状况对储量评价十分重要。本文分析了利用γ能谱中的特征峰测定铀-镭平衡系数的原理,研究了通过铀矿石的高分辨率多道γ能谱中1001.03keV谱峰和934.06keV谱峰分别推算238U、226Ra的含量并以此计算铀-镭平衡系数的数学过程。开展了铀矿模型测量实验,实验结果验证了该方法的可行性,可应用于铀矿γ测井勘探工作中。     

新疆伊犁铀矿勘探场所γ辐射空气吸收剂量率调查

以新疆伊犁铀矿勘探场所为研究对象,调查其场所环境γ辐射空气吸收剂量率水平。结果表明,铀矿勘探场所地表环境γ辐射空气吸收剂量率为当地正常本底水平。     

铀矿勘探的原有方法和新方法

在未来25年期间,将非常需要进行大规模的铀矿勘探,这就要求提高各种勘探的能力。最重要的是提高对铀矿床存在模式的地质知识,其次是改善原有勘探技术和仪器设备,同时促进对地表和深部发现铀矿体的新方法的研究和发展。国际原子能机构过去已召集了两次铀矿地质会议和一次铀矿勘探方法会议。这次会议又进一步交流了铀矿勘探技术及仪器设备方面的经验。本文是会议的第一篇报告,文中对各种方法进行了简单的评论,首先评论了原有的方法,其次评论了还没有在适当范围内应用的方法。对前30年期间所应用的14种方法进行了鉴定,简单地总结了各种方法的用途、优点和局限性。进一步研究新技术的目的是,除寻找鉴别地表矿床的新方法和手段外,主要是研究能直接探测隐伏矿体(在地面没有给出γ信号反映)的方法和仪器设备。要达到这个目的,以下两个因素是重要的:(1)研究和发展新技术和仪器要有足够的资金;(2)更多地培训铀矿探勘和仪器设计人员。会议文集中的各篇报告讨论了原有方法的发展,提出了进一步研究和发展新技术的意见及铀矿勘探实例,希望这些讨论和以后的讨论将促进勘探技术的发展,以保证今后世界核燃料的供应。     

用铀矿废石做地基的住房的放射卫生评价

在铀矿的勘探、开采和水冶过程中,产生大量废石和尾矿。国外曾报道过用铀矿尾矿做建材,会使建筑物内的γ外照射、氡-222及其子体浓度显著增高,以致部分房屋不宜居住。我省某铀矿附近,近十几年来一直有人利用铀矿废石做住房地基,特别是最近几年用得更多。为了摸清这种类型住房的辐射水平,我们于1982年对两个铀矿的四个废石场内的废石的辐射水平和某铀矿附近的八个村、镇用铀矿废石做地基的建筑物内的γ外照射、氡-222及其子体浓度作了调查,并作了放射卫生评价。     

日本民间企业恢复在尼日尔的铀矿勘探活动

几年前曾在尼日尔进行过铀矿勘探开发的日本民间探矿企业“国际铀资源株式会社”自1985年9月开始又恢复了在尼日尔的勘探活动,进一步确认伊拉万泽基兰地区的铀矿储量。至1986年4月为止已实施了钻探,判明矿量后计划与已掌握矿量的特基旦特斯姆地区同时进行论证,等待铀市场情况恢复,计划从1988年着手开发建设,1993年开始商业性生产。“国际铀资源株式会社”在尼日尔的铀矿勘探活动曾在1982年2月因铀市场不景气而告中止。该公司在尼日尔共取得28 000 km~2铀矿勘探     

总计数γ测量的标定

1975年,联邦省铀矿资源勘探计划(URP)开始采用加拿大地调局的高灵敏度γ能谱仪系统在萨斯喀彻温、马尼托巴和安大略进行航空放射性测量,1976年,按与联邦政府的合同,在计划中增加了另外3架飞机。为了使大量的γ     

国外铀矿地质普查勘探现状

最近几年,国外铀矿普查勘探活动又逐渐频繁起来,一些主要资本主义国家不仅加强和扩大在本国的普查铀矿活动,而且借合作为名在国外掠夺铀资源。如美国、日本、西德、法国的许多公司都在亚、非、拉一些国家的地区寻找铀矿。联合国所属国际原子能机构从1970年以来每年一次共召开了五次铀矿地质、勘探     

国外铀矿勘探情况

六十年代末,由于军用铀需要量的减少,核动力计划的推迟,导致了世界铀矿勘探事业的衰落,不少国家缩减或停止了铀矿勘探活动。1973年石油危机的出现,1976年石油价格的上涨,又推动了铀的勘探活动,出现了新的找铀高潮。     

Identification of radiation treatment of wheat （Triticum aestivum. L）and rice （Oryza sativa. L） samples using thermoluminescence of contaminating minerals

Food irradiation is gaining popularity worldwide and this technology is important to improve quality and reduce the post harvest losses of food. Because of the rapid commercialization of irradiated foods throughout the world, compliance of different regulations relating to use of technology in different countries and demand of consumers for clear labelling of irradiated foods, there is need for the development of analytical methods to detect radiation treatment of food. Among several methods studied so far, thermoluminescence （TL） is an important method that can be used to find out the irradiation history of food that contain even a very minute amount of dust particles. In this study, the irradiated and unirradiated wheat and rice samples were analyzed using the TL method. The samples were purchased from the local market of Peshawar and irradiated to radiation doses of 0.5 and 1.0 kGy using Co-60 gamma irradiator at the Nuclear Institute for Food and Agriculture （NIFA）, Peshawar. The mineral contaminants were isolated by jet water, ultrasonic treatment, and density gradient. TL glow curves of the isolated minerals from irradiated and unirradiated samples were recorded between the temperature ranges of 50-500℃ using a TL reader. Generally, the glow curves for irradiated samples showed much higher TL intensities （TL1） than the unirradiated samples. The results were normalized by rerradiation of mineral samples to gamma-ray dose of 1.0 kGy followed by determination of the second glow curves （TL2）. The ratio of the area of first glow curve to that of second glow curve （TL1/TL2） was calculated for selected temperature intervals and compared with the recommended values for unirradiated and irradiated samples. Finally, the shapes of the glow curves for irradiated and unirradiated samples were also analyzed. On the basis of these results （comparison of TL-intensities, TL1/TL2 ratios and shapes of the glow curves）, all the irradiated and unirradiated samples of wheat and rice were unequivocally identified.     

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。     

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.     

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.     

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.     

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.     

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.