辐照食品直线加速器电子枪设计

本文介绍了中国科技大学国家同步辐射实验室研发的一台食品辐照保鲜用直线加速器中电子枪的设计.通过枪体内电磁场模拟计算、优化电子枪形状、并且在考虑空间电荷效应情况下对电子束发射过程进行模拟,得到了满足设计要求的束斑尺寸.另外对电子枪的加工和调试过程也进行了介绍,通过电子枪高压老炼及出束实验表明,其各项参数性能均达到设计要求.另外对直线加速器螺线管聚焦线圈漏场对束流的影响也作了讨论,采用相应措施可增加磁屏蔽,减小漏场影响,保证束流品质.     

用于硼中子俘获治疗的强流质子回旋加速器中心区结构优化设计

中国原子能科学研究院目前正在研制用于硼中子俘获治疗（BNCT）的强流质子回旋加速器,该加速器设计引出能量14 MeV、质子束流强大于1 mA。相比引出流强为400 μA的PET回旋加速器,BNCT强流质子回旋加速器对中心区相位接收度和轴向聚焦的要求更高。为实现mA量级的束流的加速和引出,BNCT强流质子回旋加速器采取了增加负氢束流注入能量、增大磁铁镶条孔径、使用用于增大Dee盒头部张角的阶梯状结构及调整加速间隙的入口和出口高度等一系列中心区结构优化设计,有效地提高了中心区的相位接收度,改善了轴向电聚焦。在新的离子源注入能量下通过数值计算得到实测场下的轴向电聚焦和间隙高度的关系,选取合适的间隙高度获得最佳的轴向聚焦,从而确定了mA量级束流的注入和加速的中心区结构。同时在设计中考虑空间电荷效应的影响,计算了不同流强下的束流尺寸变化。中心区结构在实测磁场下的优化设计计算结果表明,BNCT强流质子回旋加速器中心区的束流对中好于0.5 mm,相位接收度大于40°,中心区最高可接收流强3 mA。目前,新的中心区结构已进入机械加工阶段。     

15-20mA负氢离子源的设计

制约强流质子回旋加速器技术发展的一个主要因素是离子源的束流强度以及束流品质，为提高引出流强、改善束流品质，中国原子能科学研究院一直致力于离子源的发展。2000年建成了平均流强5．2mA的负氢离子源，束流发射度达到了0．65πnm-mrad，2004年建成了高于10mA的负氢离子源。为进一步提高束流流强，满足中国原子能科学研究院串列加速器升级工程的需求，在原有10mA负氢离子源基础上设计1台新的离子源，将平均引出束流提高到15-20mA。     

纵向多灯丝电子帘加速器的束流不均匀度

束流不均匀度是电子帘加速器束流性能的一重要指标。影响束流不均匀度的主要因素是加速器结构中各电极（阴极、反射极、栅极、阳极）的电位、形状及其相对位置。本工作针对1台纵向多灯丝电子帘加速器的实际结构参数,计算其束流不均匀度,通过分析和比较,讨论了进一步改善束流不均匀度的可能途径,为改进电子帘加速器的设计提供了参考。     

电子能量损失谱仪用中高能电子枪的研制

研制了一台电子能量损失谱仪用的中高能电子枪。其产生的电子与原子、分子发生碰撞,通过谱仪收集、分析散射电子的动量和能量,可以获得靶的电子结构和碰撞动力学信息。该电子枪结构简单,由热阴极、栅极、阳极、聚焦极和偏转板组成;电子能量可调范围大(1-3 keV),操作简单。为了获得最优的束流条件,利用SIMION电子光学软件模拟了电子发射源大小和初始发散角对靶点处的束斑大小和束流发散角的影响。在电子能量为1.5 keV条件下,实验检验给出在离电子枪出口27 mm处可获得束径约为0.95 mm、束流发散角约0.93°和束流强度6.27mA的电子束,满足电子能量损失谱仪的使用要求。     

高压型低能大功率辐照加速器电子枪研制

低能大功率辐照加速器广泛用于辐照加工产业。本工作研制出一台二极电子枪作为高压型低能大功率辐照加速器的电子源,并通过出束实验对其加以优化,最后确定了二极电子枪的最佳结构、尺寸及运行参数等。结果表明,从电子枪引出电子束的能量为5~25 keV,流强为60~100 mA,束斑为15~30 mm,半散角为0.6°~1.6°,不稳定度好于±0.6%。该电子枪工作稳定,寿命长于5 000 h。     

宽范围高精度电子枪控制系统的研制

本文针对"1.2 MeV/10 mA高频高压型电子加速器及束线"项目中钨丝阴极热发射电子枪的控制需求,在了解了系统组成和工作原理的基础上,采用三极式平板热阴极发射电子枪,阴极材料使用钨丝,灯丝加热电源由发电机供电,引出电压从加速管电极分压获得。通过设计一种基于可编程逻辑控制器(Programmable Logic Controller,PLC)的控制系统,实现了电子枪引出1μA～50 mA 4个数量级范围的直流电子束。该控制系统采用PLC作为设备控制器,LabVIEW软件作为用户界面,通过通信协议(Object Linking and Embedding for Process Control,OPC)接口实现控制软件与设备控制器的通讯。实验测试表明,系统具有可靠稳定、灵活高效等特点。     

1.2 MW加速器电子光学系统静态、动态模拟

PIC(Particle in cell)编码能跟踪数千个宏粒子,已经成为研究束流物理的重要工具.本文介绍了PIC模拟方法;并用静态、动态模拟软件对中国工程物理研究院研制的1.2 MW加速器电子光学系统进行模拟.结果显示:随着加速器束流强度增加,加速管出口处束斑半径先逐渐减小,然后逐渐增大.在束流为250 mA左右时,束斑半径达到最小,此时两模拟结果之间的差异为7%;在500 mA时,束斑半径与小束流时相当,两模拟结果之间的差异达到了29%.     

中国原子能科学研究院紧凑型强流质子回旋加速器剥离引出技术研究

中国原子能科学研究院(CIAE)在20世纪90年代建造了一台30 MeV紧凑型强流质子回旋加速器后,经过近30年的发展,先后自主研发成功了基于剥离引出技术的能量为10 MeV、14 MeV、100 MeV、硼中子俘获治疗用14 MeV/1 mA等系列能量的紧凑型强流质子回旋加速器。建成的100 MeV紧凑型强流质子回旋加速器(CYCIAE-100),是目前国际上能量较高的一台紧凑型强流质子回旋加速器,最高流强达到520 μA,束流功率达到52 kW。建成的硼中子俘获治疗用的质子回旋加速器,也是我国首次自主研发成功的引出质子束流强达到mA量级的强流质子回旋加速器。在系列能量的紧凑型强流质子回旋加速器研发过程中,CIAE对剥离引出后的束流色散效应、剥离膜与束流夹角对引出后的束流品质的影响、单圈剥离引出技术等紧凑型强流质子回旋加速器剥离引出技术等方面展开了研究,且自主开发出了剥离引出计算程序,为紧凑型强流质子回旋加速器的应用作出了贡献。     

产额大于1.5×1010n/s中子管引出/加速系统的物理设计

根据高产额(>1.5×1010n/s)中子管对引出/加速系统的要求,完成了在180kV引出/加速电压下,加速离子束流1.1mA的新型屏蔽式引出/加速系统的物理设计,与普通中子管比较,加速电压增加50%,束流增加一个数量级,中子产额增加一个数量级,实现了系统的结构优化.经长期实践考验证明,系统的物理设计合理,为更高产额中子管的研制奠定了基础.     

Sorption methods of separating barium and radium,aluminum and gallum,and zirconium and hafnium

Chromatographic methods of separating elements with very similar properties have now been developed. However, a number of these methods are difficult to use industrially as their throughput is low. The efficiency of chromatographic separation methods could be increased considerably by using appropriate complex formers, which decrease the effective concentration of the ions being separated, and,in the first approximation, this is equivalent to a decrease in the amount of elements being separated. The difference in the formation constants of the complex compounds increases the separation coefficient. By investigating chromatographic separation with the use of various complex formers, we found the optimal conditions for separating barium and radium, zirconium and hafnium, and aluminum and gallium. The throughput of these methods, with respect to the macroelement was 15–60 kg/hr per m² of column cross section.     

医源性电离辐射损伤及其生物医学防护

随着核与辐射技术在医学检查、诊断和治疗领域运用的增加,世界范围受照人群不断增多,医源性辐射已成为人类最主要的人工辐射来源之一。医疗机构和个人在选择利用放射手段获取诊断和治疗利益的同时,需要注意和防护伴随的辐射损伤效应。本文介绍了医源性辐射及其危害、机体组织的辐射损伤特性和类型、辐射生物效应分子及效应调节研究的进展,简要概述目前临床已经使用或最具应用潜力的辐射防护策略。     

Distribution and Fixation of Cesium and Strontium in Zeolite A and Chabazite

The selective removal and fixation of Cs and Sr have been studied in zeolite A and chabazite. Cesium ion was preferentially distributed into chabazite with a high distribution coefficient (K _Cs>10³ cm³·g^?1) in the presence of NaCl (10^?1 mol·dm^?3). The K _Sr values for zeolite A attained about 10³ cm³·g^?1 in the pH range of 8～10, and they gradually decreased with an decrease in pH.

The initial rate of Cs adsorption was fairly fast in chabazite, and the adsorption ratio reached almost 100% within a few hours. The adsorption ratio of Sr in binderless A zeolite reached almost 100% after 15 h. The adsorption of Cs and Sr on these zeolites was followed by Langmuir-type isotherm. Cesium forms of these zeolites recrystallized to pollucite (CsAlSi₂O₆) above 900°C for zeolite A and above 1,200°C for chabazite. As for Sr forms, these zeolites changed to SrAl₂Si₂O₆ above 900°C.

These recrystallized phases were suitable hosts for the immobilization of Cs and Sr in the nuclear waste solutions.     

清洁解控和退役若干动向与新发展

对国际辐射防护协会第 1 0届大会 ( IRPA-1 0 )涉及的清洁解控和退役问题作了论述 ,包括排除、豁免、清洁解控和废物最少化 ;退役工程技术的发展 ,包括去污技术、切割解体技术、探测技术 ;介绍了一个研究堆退役例子和加速器退役 ;最后 ,还论及了退役中受关注的一些问题 ,如 :石墨废物、混凝土废物、重水堆退役的氚防护、退役时间和退役废物量等。     

全国核与辐射安全监管信息系统的研究和建议

文章简要介绍了全国核与辐射安全监管信息系统的前期规划建设情况,包括基本建设内容、系统总体架构、以及工作中发现的影响和制约工作开展的主要问题,并提出了建议。     

Development and diversity and defense-in-depth application of ABWR feedwater pump and controller model

This work developed an advanced boiling water reactor (ABWR) feedwater pump and controller model, which was incorporated into Personal Computer Transient Analyzer (PCTran)-ABWR, a nuclear power plant simulation code. The feedwater pump model includes three turbine-driven feedwater pumps and one motor-driven feedwater pump. The feedwater controller includes a one-element/three-element water level controller and a specific feedwater speed controller for each feedwater pump. The performance tests, including step change of dome pressure, feedwater pumps transfer, inadvertent closure of all turbine control valves, and one feedwater pump trip at 100% power, demonstrate the feasibility of dynamic response of stand-alone model and incorporated model. Furthermore, a diversity and defense-in-depth analysis is performed to demonstrate the feasibility for motor-driven feedwater pump as an emergency core cooling system (ECCS) automatic diverse back-up. In Lungmen nuclear power plant (NPP), a diverse manual initiation means for the high pressure core flooder (HPCF) loop C is designed as the back-up of digitalized engineered safety features actuation system (ESFAS). If the motor-driven feedwater pump (MDFWP) can be an automatic digital diverse back-up for ESFAS, Lungmen NPP would be more robust to defend against software common-cause failure (CCF).     

Plastic and dissipated work and stored energy

This paper depicts one theoretical and experimental method to take into account the energy phenomena, associated with the elasto—plastic deformation process, during the elaboration of behaviour laws. The energy balance definition is examined in order to relate the stored energy of cold work to the hardening state variables. Two experimental approaches are used to study the evolution of the energy balance. The first one uses microcalorimetric technique and the second infrared technique. Several industrial metallic materials are studied by both approaches. Energy data are used to control the validity domain of the classical behaviour laws and to elaborate new more appropriate ones. Therefore, the hardening parameters cannot be identified with the thermodynamical forces. The use of energy considerations allows the definition of new thermodynamical forces and state variables, in the case of isotropic or kinematical hardening.     

Construction and operational experience with small and medium power reactors and expected improvements

Past experience with small and medium power reactors (SMPRs) in the areas of construction and operation is examined in this paper. Current development of SMPRs focuses on passive safety features; larger design and safety margins; reduction of construction periods through simplification, modularization and increased shop fabrication.