附银硅胶除碘的机理研究

本文用红外吸收光谱测定、扫描电镜观察、X射线衍射分析、放射性示踪试验等方法,研究了附银硅胶除碘的机理。结果表明,附银硅胶中的银仍以AgNO_3形式存在,吸碘后的反应产物有Agl和AgIO_3,在本实验条件下,其中AgI与AgIO_3的摩尔比大约为3:1。     

放射性物品分类方法研究

放射性物品种类繁多，不同放射性物品的特性和潜在环境风险不同，国内对放射性物品进行分类管理，并且制定了《放射性物品分类与名录（试行）》。为优化国内放射性物品分类，本文调研了国内外放射性物品分类现状以及分类的依据，总结了分类依据的主要差异，剖析了国内放射性物品分类及其依据中存在的问题，提出解决问题的思路和建议：一是删除放射性物品分类中放射源、放射性废物等列举事项；二是修订分类与目录，不同分类放射性物品对应的联合国编号唯一，与国际保持一致。本文为《放射性物品运输安全管理条例》及《放射性物品分类与名录（试行）》修订提供了参考。     

新型缩氨基硫脲化合物的合成及其抗癌活性的研究

合成了6种2乙酰噻吩缩氨基硫脲,其中5种为首次合成的新物质。用红外、质谱和元素分析等方法对合成的6种化合物进行了指认。化合物的体外抗癌活性表明,它们对3种癌细胞均有一定的抑制作用。用111In标记的6种化合物的动物试验表明,放射性标记物随血液循环没有明显的定向浓集。能否为体内肿瘤细胞所摄取,有待进一步研究。     

球床高温气冷堆核电站放射性废物最小化策略研究

放射性废物最小化是放射性废物管理的基本原则之一。高温气冷堆核电站放射性废物最小化策略研究对于优化设计与运行实践和全寿期放射性废物管理,以及高温气冷堆产业化发展具有重要意义。通过对世界上主要球床高温气冷堆运行历史和放射性废物数据的调研和论证,分析了球床高温气冷堆技术及其放射性废物特点,总结了高温气冷堆放射性废物管理值得借鉴经验及相关研究进展,提出了高温气冷堆核电站全寿期放射性废物最小化的策略和建议。     

伴生放射性废物管理探讨

叙述了部分国家伴生放射性废物管理实践和一些国际组织对伴生放射性废物管理的建议,分析了我国伴生放射性管理方面存在的突出问题。提出了加强我国伴生放射性废物管理的建议,即在全面调查的基础上,制定专门的伴生放射性管理规章。最后给出了当前伴生放射性废物的管理政策建议。     

3-正丁基锡-N-琥珀酰亚胺苯甲酸酯的合成及其125I标记

合成了3-正丁基锡-N-琥珀酰亚胺苯甲酸酯（ATE）和N-琥珀酰亚胺-3-碘苯甲酸酯（SIB），其产率分别为45．4％和71．4％，并用核磁、质谱、红外等对它们的结构进行了表征。对ATE进行了^125I标记，得到S^125IB，标记率可达93．0％，放化纯度〉98．0％。本方法为放射性药物碘的间接标记提供了重要参考。     

压水堆核电站检修过程中气载放射性源项及防护

介绍了压水堆核电站检修过程中的气载放射性源项:放射性气溶胶、放射性碘和放射性惰性气体,对3种源项的特点及其辐射防护分别进行了说明。     

我国核电厂放射性废物管理进展及挑战

分析了我国核电厂放射性废物管理现状;指出了核电厂放射性废物管理面临的挑战;提出了包括进一步完善法规标准、完善放射性管理体制、加强群堆核电厂放射性废物管理、鼓励技术创新和产学研结合等加强核电厂放射性废物管理的应对措施。     

加速器屏蔽体中氚的提取和比活度测量

使用红外炉发展了一种从活化混凝土中提取氚的方法。通过研究氚的提取效率与加热温度、加热时间的关系,获得了氚的提取优化条件为在800℃下加热30min,Ar气流量设置为200mL/min。氚由两个冷凝管收集,然后装到1个小玻璃瓶中,与液体闪烁体混合,使用液体闪烁计数器计数。使用这种方法提取氚只需55min。相对于使用电子炉提取氚的方法,氚的提取效率可达到100%。收集了两个加速器屏蔽体中的混凝土样品,测量了样品中的γ射线核素和氚的放射性比活度。结果显示,氚的比活度与¹⁵²Eu和⁶⁰Co的比活度有很强的相关性。可得出结论：氚主要产生于热中子俘获反应⁶Li(n,α)³H。因而,可使用⁶⁰Co的放射性比活度简单估计活化的混凝土样品中氚的放射性比活度。     

放射性三废设施全年安全运行

2008年,放射性废物处理和运行中心接收放射性废液约90m3,收贮放射性固体废物近30m3,净化处理放射性废气约1．6亿m3。放射性废液综合处理车间水泥固化线自2007年11月开始运行以来,共处理了放射性废液200多m3,产生了水泥固化体近3000桶,实现了安全运行无事故200d,有效缓解了我院放射性废液暂存库过满的安全隐患。     

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。     

核电站设备可靠性数据库的建立与应用

以大亚湾核电站为例,论述了核电站设备可靠性数据的采集与处理、可靠性参数的分析计算方法及可靠性数据库的建立与应用等。数据源涉及到设备的设计信息、运行信息、维修信息、定期试验记录等。在大亚湾核电站运行经验的基础上,形成了大亚湾核电站设备可靠性数据库,为深入地、客观地记录核电站各类设备的运行历史和现状、监控电站设备,特别是与安全相关设备的状态,提供了有效的工具;为加强设备的可靠性与可用性管理、确保电站的安全经济运行,提供了非常有实用价值的信息;同时还为核电站的安全管理、可靠性分析、概率安全评价、以可靠性为中心的维修及经济性管理等领域里的新技术在核电站的应用研究与开发,提供了必不可少的数据。     

Guidance for Package Approvals in the United Kingdom

Abstract

Approval is required under the transport regulations for a wide range of package designs and operations, and applications for competent authority approval and validation are received from many sources, both in the UK and overseas. To assist package designers and applicants for approval, and to promote consistency in applications and their assessment, the UK Department for Transport issues guidance on the interpretation of the transport regulations and the requirements of an application for approval and its supporting safety case.The general guidance document, known as the Guide to an Application for UK Competent Authority Approval of Radioactive Material in Transport, has been issued for many years and updated to encompass the provisions of each successive edition of the IAEA transport regulations. The guide has been referred to in a number of international fora, including PATRAM, and was cited as a 'good practice' in the report of the IAEA TRANSAS appraisal of the UK in 2002. Specialist guides include the Guide to the Suitability of Elastomeric Seal Materials, and the Guide to the Approval of Freight Containers as Types IP-2 and IP-3 Packages. This paper discusses the guidance material and summarises the administrative and technical information required in support of applications for approval of package designs, special form and low-dispersible radioactive materials, shipments, special arrangements, modifications and validations.     

Developments and needs in nuclear analysis of fusion technology

Nuclear analyses provide essential input to the conceptual design, optimisation, engineering and safety case of fusion technology in current experiments, ITER, next-step devices and power plant studies. Calculations are intricate and computer-intensive, typically requiring detailed geometry models, sophisticated acceleration algorithms, high-performance parallel computations, and coupling of large and complex transport and activation codes and databases. This paper reports progress on some key areas in the development of tools and methods to meet the specific needs of fusion nuclear analyses. In particular, advances in the production and modernisation of reference models, in the preparation and quality assurance of acceleration algorithms and coupling schemes, and in the evaluation and adaptation of alternative transport codes are presented. Emphasis is given to ITER-relevant activities, which are the main driver of advances in the field. Discussion is made of the importance of efforts in these and other areas, considering some of the more pressing needs and requirements. In some cases, they call for a more efficient and coordinated use of the scarce resources available.     

The effect of oxidation and crystal phase condition on the ballooning and rupture behavior of Zircaloy-4 cladding tube-under transient-heating conditions

In order to investigate the effect of oxidation and crystal phase condition on the ballooning and rupture behaviors of cladding tube under simulated loss-of-coolant-accident conditions, laboratory-scale experiments were performed in which internally pressurized non-irradiated Zircaloy-4 (Zry-4) cladding specimens were heated to burst in steam and argon gas conditions. Values of the maximum circumferential strain were normalized by dividing them by engineering hoop stress at the time of rupture. The dependence of the normalized value on burst temperature and the relationship between the normalized value and the length, width and area of rupture opening were evaluated. The correlation between the normalized value and the burst temperature suggested that the fraction of the β-phase in Zry-4 cladding specimens affected the strain in the specimens and the oxidation of specimens suppressed the amount of ballooning of the specimens. The relationship between the normalized value and the length, width and area of rupture opening indicated that the length, width and area of rupture opening depended on the crystal phase condition in Zry-4 cladding specimens irrespective of atmosphere in the case of the heating rate of ～3 K/s.     

Plan of ITER remote experimentation center

Plan of ITER remote experimentation center (REC) based on the broader approach (BA) activity of the joint program of Japan and Europe (EU) is described. Objectives of REC activity are (1) to identify the functions and solve the technical issues for the construction of the REC for ITER at Rokkasho, (2) to develop the remote experiment system and verify the functions required for the remote experiment by using the Satellite Tokamak (JT-60SA) facilities in order to make the future experiments of ITER and JT-60SA effectively and efficiently implemented, and (3) to test the functions of REC and demonstrate the total system by using JT-60SA and existing other facilities in EU. Preliminary identified items to be developed are (1) Functions of the remote experiment system, such as setting of experiment parameters, shot scheduling, real time data streaming, communication by video-conference between the remote-site and on-site, (2) Effective data transfer system that is capable of fast transfer of the huge amount of data between on-site and off-site and the network connecting the REC system, (3) Storage system that can store/access the huge amount of data, including database management, (4) Data analysis software for the data viewing of the diagnostic data on the storage system, (5) Numerical simulation for preparation and estimation of the shot performance and the analysis of the plasma shot. Detailed specifications of the above items will be discussed and the system will be made in these four years in collaboration with tokamak facilities of JT-60SA and EU tokamak, experts of informatics, activities of plasma simulation and ITER. Finally, the function of REC will be tested and the total system will be demonstrated by the middle of 2017.     

高温气冷堆石墨构件的碰撞力学行为研究

高温气冷堆的反射层和隔热层主要由数量庞大的石墨砖和碳砖组成,在地震或冲击载荷作用下,部件之间可能发生滑移和碰撞,影响其结构完整性。简化的数值分析模型是研究这种大规模散体结构的重要手段,而其中模拟碰撞的非线性连接单元参数对分析的收敛性和结果的准确性至关重要。本文对高温气冷堆中石墨构件的3种典型碰撞形式进行了实验研究,测量得到了各碰撞模式下碰撞时间和恢复系数与碰撞速度的关系。针对碰撞实验中边界条件与堆内实际构件的差别,采用商业有限元分析软件ABAQUS对不同碰撞形式进行了数值分析,进一步获得了更为准确的碰撞特性,并通过改进的Hertz碰撞模型对实验和数值结果进行分析,得出了非线性碰撞连接单元的等效刚度系数和等效阻尼系数。最后利用数值分析方法进行了与堆内构件设计相关的质量和间隙尺寸对碰撞单元等效刚度系数和等效阻尼系数的详细研究,为高温气冷堆石墨和碳堆内构件的设计提供参考。     

海水提铀技术最新研究进展北大核心CSCD

天然铀是保障国家核能持续稳定发展的重要物质基础。海洋蕴含有丰富的天然铀资源,从海水中提取铀,对于补充完善我国铀供应体系,实现天然铀供应自主化具有重要战略意义和经济意义。本文综述了近年来海水提铀技术研究方向的最新进展。主要总结了国内外海水提铀吸附材料、海试试验等研究结果,并对未来海水提铀工程化发展进行了展望。     

Adsorption of iodine on graphite in High Temperature Gas-Cooled Reactor systems: A review

Adsorption of iodine on graphite is of great interest for operation and safety of high temperature nuclear reactors. Graphite can adsorb significant amounts of iodine and retain it for a long period of time. Significant amount of work on this subject has been done in the past. Various types of adsorption apparatus have been designed and data were collected. The types of graphite used in past studies are not available anymore, and as a consequence the data are not applicable for the new type of commercial nuclear grade graphites. However, the past experimental systems, data, and their analysis are useful to design a better experimental system, collect more accurate data, and, provide better understanding of the adsorption process and data. In addition the existing data can be used to generate a framework to understand the types of adsorption processes taking place. In this work, we have conducted an exhaustive literature review and further analyzed the data. Four adsorption isotherms; the Langmuir, the Freundlich, and the two isotherms proposed in the International Atomic Energy Agency (IAEA) Tecdoc-978 were used to correlate the available equilibrium adsorption data. For most of the data, the simple Langmuir and the Freundlich isotherms provided a reasonable fit of the data. The Polyani's potential theory was also used to check the consistency of the data and as indicated by the theory, most of the data set provided a single characteristic curve. The isosteric heats of adsorption calculated using the literature data suggested that iodine-adsorption on graphite could be a chemisorption process.     

The influence of charge characteristics of suspension droplets on the ion flow field in different temperatures and humidity

In order to clarify the charging characteristics of suspension droplets in ion flow field under different temperatures and humidity, the effective charging factor used to characterize the charging characteristics of suspension droplets is introduced in this paper, and a calculation method of charging factor is proposed based on the upstream finite element method (FEM). Then, the charging factor under different temperatures and humidity is calculated, and the analytic expression of the charging factor considering the influence of temperature and humidity is obtained by fitting the calculation results. The influence of suspension droplets on the ion flow field is analyzed. The results show that the charging factor is small and increases little with the relative humidity when the relative humidity is less than 60%, and the charging factor is large and increases rapidly with the relative humidity when the relative humidity is more than 60%. At the same relative humidity, the charging factor increases linearly with the temperature. The influence of charged suspension droplets on the ion flow field can be ignored when the relative humidity is less than 60% and must be considered under high temperature and humidity. The calculation method and analytic expression of the charging factor proposed in this paper can be used to model of ion flow field considering the influence of temperature and humidity and provide technical support for the construction of HVDC transmission lines across high temperature and humidity.