在辐射防护和安全中的一些概念的转变

本文讨论了在辐射防护和安全中一些概念的转变，其中主要是：用“实践”和“干预”的观点代替单一的“实践”的观点；用辐射防护体系代替单一的剂量限值；用一般职业保健服务的观点代替以发现辐射效应和放射性禁忌症为目的的医学监护的观点，用以处置为中心，包括废物的产生，处理，前处置和处置在内的全面的放射性废物管理代替以临时贮存为终点仅包括收集和贮存的废物管理。并注意正确理解“约束”的概念，加强核设施的防护，加强天     

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《放射性固体废物贮存与处置许可管理办法（草案）》审议并通过
　　2013年12月5日环境保护部召开的环境保护部部务会议,审议并原则通过了《放射性固体废物贮存与处置许可管理办法（草案）》,该草案主要内容由中国辐射防护研究院三废治理研究所环保部技术支持项目组主持编制,也是项目组截至目前编制的最高层次的法规标准。部务会认为,为加强放射性固体废物贮存和处置活动的监督管理,规范放射性固体废物贮存和处置许可,有必要根据《中华人民共和国放射性污染防治法》和《放射性废物安全管理条例》,制订本《放射性固体废物贮存与处置许可管理办法（草案）》,对许可证申请、许可证审批及法律责任等做出规定。会议决定,《放射性固体废物贮存与处置许可管理办法（草案）》经进一步修改后发布施行。     

放射性废物管理与辐射防护新进展

本文探讨了近十年来辐射防护的研究进展对放射性废物管理特别是对放射性废物处置所产生的影响及进一步研究的课题。     

油气工业中放射性废物的处理和处置

油气的开采会产生大量的放射性废物,对放射性废物的处理与处置事关公众和环境的辐射安全问题。本文从油气工业放射性废物的源项和存在形式等特征出发,对放射性废物的临时贮存、污染设备的去污及放射性废物的处理、处置过程中涉及的技术方法和相关管理要求进行了介绍,为实践中选择合理可行的处理、处置方案以及建立油气工业放射性废物监管体系提供借鉴和参考。     

国外混合燃料快堆放射性废物管理概况

本文介绍了国外混合燃料快堆系统的燃料元件生产厂、快堆和乏燃料后处理厂产生的放射性废物的来源、组成、特点及其处理、贮存和处置，并介绍了快堆放射性废物管理发展趋势。     

德国做出转移放射性废物的决定

<正>【世界核新闻网站2010年1月18日报道】德国联邦辐射防护局(BfS)已决定将约12.6万桶放射性废物从阿塞(Asse)放射性废物处置设施中转移出去。这些放射性废物将从地下转移至地表进行临时贮存。这些废物大部分属于低放废     

辐射防护新概念对放射性废物管理的启发意义

本文通过对源项、途径、剂量、效应的讨论，进一步明确放射性废物管理的地位和作用；通过对实践、干预、豁免和潜在照射的讨论，增强在放射性废物管理中正确使用辐射防护原则的认识；通过对市管体系、现场防护体系、事故应急体系的讨论，促进国际放射防护委员会的建议在放射性废物管理中的实施。     

民用放射性废物管理设施许可管理探讨

放射性废物管理设施通常包括放射性废物处理、贮存和处置设施,依据法规规定,放射性废物处理、处置设施属于民用核设施范畴,因此,民用放射性废物管理设施应按照《民用核设施安全监督管理条例》申领核设施建造、运行许可证等。我国现有放射性废物管理设施数量多,现状和特点不尽相同。当前,部分民用放射性废物管理设施存在范畴划分不明确、管理模式不统一等问题。结合我国民用放射性废物管理设施实际情况,简要梳理和探讨其许可管理方式。建议:独立场址放射性废物管理设施应统一纳入民用核设施管理范畴并申领民用核设施安全许可证;民用核设施配套建设的放射性废物管理设施,应依据主体设施的差异实施分类许可管理为宜。     

我国放射性废物管理模式涉及的主要方面

本文介绍了在实践中逐步形成和完善的我国放射性废物管理模式所涉及的主要方面,包括：废物管理体系的确立和核设施内部废物管理机构的设计,以安全为目的,处置为核心的从“出生到坟墓”的全过程管理,放心物最小量化,废物审计,废物跟踪制度,对废物从产生到处置的全过程实行许可证制度。     

低放废物处置场辐射防护设计关键问题研究

低放废物处置场辐射防护设计一般主要涉及废物处置单元和废物接收厂房。废物处置单元根据处置场接收准则、废物码放处置方案等进行辐射防护设计,废物接收厂房的辐射防护设计主要关注废物装卸区、开箱倒装区、无损检测区等。本文主要介绍了低放废物处置场辐射分区准则的制定,辐射防护设计原则的考虑,废物处置单元及废物接收厂房辐射防护设计等方面的内容。重点关注了废物处置单元废物分层、分隔断码放处置情景,不同分隔码放方式所允许码放处置的放射性废物表面剂量率限值,码放层数限制,处置单元侧墙直接照射、处置单元天空散射、水泥砂浆及封顶的辐射防护设计考虑,以及废物接收厂房开箱倒装区的辐射防护设计关键问题。介绍了低放废物近地表处置场辐射防护设计相关的问题处理及经验,为相关设施辐射防护设计提供了参考。     

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.