基于氦喷嘴带传输装置的微机数据获取系统

介绍一套特殊的核物理实验装置，它由氦喷嘴装置，带传输装置和微机数据获取与分析系统组成，氦喷嘴装置和带传输装置将反应物从反应室传送到探测器前面，同时给出一个同步信号来控制获取系统，获取系统准确识别控制信号，产生一个明显的标识符来标记不同的样品。本系统对短寿命远离稳定线纱的研究有独特的优势。     

电子束辐照交联线缆张力调节装置

张力调节装置是电子束辐照交联电线电缆生产线传输系统实现速度同步的关键部件。装置有多种类型合理配置不同形式的张力调节装置，可保证生产线正常运行和提高产品的质量。对两种立式张力调节装置的工作原理、特点进行了论述，并对如何建立张力进行了分析阐述。     

“天光一号”激光装置实时监测系统

利用“天光一号”激光装置开展激光靶物理实验的过程中，传输到靶面的能量、脉冲宽度和波前均匀性对物理实验的结果起到决定性的作用。为保证装置的稳定运行，同时实现对装置运行状况的实时获取、分析和评估，逐步建立起“天光一号”激光装置实时监测系统。     

高能X射线成像装置数据采集与传输系统设计

为满足高能X射线成像装置对并行数据实时采集以及远距离传输的要求,开发了一套嵌入式并行数据采集与网络传输系统。该系统用FPGA实现多通道并行数据的实时采集,用ARM完成了数据的缓存以及基于TCP协议的以太网数据传输。此系统已成功应用于多台高能X射线成像装置中,运行稳定。     

CARR仪器中子活化分析自动控制系统设计

在中国先进研究堆设计了一套新的仪器中子活化分析自动控制系统。系统主要由辐照管道、样品架、样品转换器、传输装置和3套可同时连续24h工作的HPGe探测器组成。测量盒内装有无线射频识别(RFID)电子标签,对样品进行实时跟踪和定位。压缩空气作为样品传输动力。系统由组态王Kingview6.55、可编程逻辑控制器(PLC)控制,可实现批量样品辐照、冷却、测量等一体化控制。     

直通道磁元件磁场测量

为使重离子束从注入器（ＳＦＣ）不经主加速器（ＳＳＣ）直接传输到实验终端。最近在兰州重离子研究装置（ＨＩＲＦＬ）上新建了直通管道系统。在该系统中有３台偏转磁铁和３台四极透镜。本文叙述了它们的测磁内容和方法，给出了激磁曲线、径向和轴向场分布、磁场梯度、等效长度等结果。结果表明：全部符合原设计要求，并有一定的余量。     

Study on Automated Search, Location and Precise Re-location μm-size Particles

在分离短寿命裂变产物时，辐照后的样品经“气动传输系统”传出后，需将样品从样品盒中取出。因研究对象是半衰期为分钟级的短寿命核素，取样时间应尽可能的短。刚辐照后的样品剂量水平为居里级。为此，本工作针对液体样品的快速切割取样进行了研究，并成功研制出“自动切割取样装置”。     

10MeV大功率电子辐照加速器微波系统研制

10MeV大功率电子辐照加速器是采用行波加速结构的电子直线加速器。微波系统是它的重要组成部分之一，该系统包括微波的产生、传输、监测及保障速调管和波导窗安全可靠运行的驻波比快速成保护装置和保证微波系统稳定工作的充气装置。本系统采用高稳定度的晶振锁相式信号源和350W固态功率放大器作为高功率放大器一速调管的激励级，速调管工作中心频率2856MHz，带宽1MHz。     

85 气体射流反冲传输装置的建立

为了对短寿命裂变产物核素进行连续收集，我们在中国原子能科学研究院重水反应堆上建立了一套气体射流反冲传输装置。该装置能将短寿命裂变产物从辐照靶所在的高辐射场区快速而有效地传输到远离靶的低本底区进行测量或进一步分离。该装置的特点是：辐照靶可反复使用，且不需对靶进行处理；传输快，适宜对裂变产物进行在线分离采集。气体射流反冲传输装置的原理基于轰击粒子（或裂变过程）使反应产物原子得到足够的反冲动能而与固体靶实现瞬间物理分离.     

串列加速器-子注入机-射电镜联机系统的建立

建立了由2×1.7MV串列加速器、200kV离子注入机、H800型透射电子显微镜和联机传输系统组成的我国第1套串列加速器 离子注入机 透射电子显微镜联机装置。对主要设备进行了改造，并采取有效措施解决了联机装置的隔震问题。2台加速器和所有的真空泵都运行时，电镜仍可正常工作，观察到的图像质量不受振动影响。电镜室内样品倾斜角最大可达52°以上，离子注入不影响电镜观测，可进行离子注入的原位和实时结构研究。离子注入机输出的115keV氮离子在电镜入口测得的束流强度达100～180nA。初步实验已原位观察到氮离子注入导致单晶硅非晶化的过程，显示这套装置具有离子注入条件下的原位观测能力。     

基于Gamma全吸收型BaF2探测装置的数据获取系统

为精确测量keV能区的中子俘获反应截面,研制了一套基于Gamma全吸收型BaF₂探测装置的数据获取系统。数据获取系统工作在Linux环境下,应用FlashADC采集探测器的脉冲信号。程序控制、数据存储、在线监控与分析程序基于Root平台。通过测量⁶⁰Co和¹³⁷Cs源,得到了数据获取系统主要性能的测试结果,其满足GTAF装置精确测量中子俘获反应截面的要求。     

固定式中子剂量仪器现场标校方法研究

本文利用小型可控中子源和中子剂量参考仪器组成的核设施现场标校系统,通过空间位置对称条件下的待校准仪器与参考仪器对中子管出射中子响应之比,得到校准系数;为了完成仪器的周围剂量当量校准系数从国家标准计量检定中心参考辐射场到核设施现场的传递,必须对其进行能量修正。通过Am-Be中子源模拟核设施内部辐射场,在其中进行中子剂量仪器现场标校实验,并与校准过的多球中子谱仪测量结果相比较。结果表明:使用未经修正的校准系数对待校准仪器的测量结果进行校准,周围剂量当量率相对偏差为17.0%;使用修正后的校准系数对待校准仪器的测量结果进行校准,周围剂量当量率相对偏差为-2.4%。     

UK fusion technology experimental activities at the ASP 14 MeV neutron irradiation facility

In support of the technological requirements for fusion, the UK fusion technology programme is conducting several experiments using the ASP DT neutron irradiation facility at Aldermaston. The present experimental programme covers two key areas of technology development: improving the quality of nuclear cross-section data required for fusion-related materials; and benchmarking fusion nuclear analysis tools such as the shutdown activation dose system MC-R2S. The first of these areas is the focus of this paper.The work presented here gives a technical overview of the ASP facility, including the accelerator, the irradiation cell, the recently re-commissioned fast sample extraction system and ancillary radiation metrology equipment. Results from preliminary activation experiments using high purity elemental- and fusion-relevant material foils, are presented. These include measurements of short-lived activation products conducted via gamma spectrometry methods.     

Preliminary study on capsule material for ITER neutron activation system

A neutron activation system (NAS) measures neutron fluence at the first wall and the total neutron flux from plasma, providing the fusion power evaluation. A pneumatic transfer method is conventionally utilized to transfer encapsulated activation samples between the irradiation stations and counting station. The temperature of the irradiation station, near the first wall could reach too high for the conventional polymer-based materials, such as polyethylene, to be used as a capsule material for the ITER NAS. Considering the environment of the irradiation station of the ITER NAS, the candidate capsule materials are chosen as four materials: RAFM (reduced activation ferritic martensitic) steel, SiC_f/SiC composite, tungsten, and CFC (carbon fiber-reinforced carbon). Preliminary investigation reveals that the CFC is the most promising capsule material for ITER NAS due to its good thermal and magnetic properties as well as low activation by neutron irradiation. Various kinds of mock-up capsules are fabricated using CFC with the consideration of the volume of inner space accommodating activation samples. Preliminary pneumatic transfer experiments carried out in the small-scale test-bed suggest that the transfer speed of capsule should be slower than 10 m/s and the wall thickness of the capsule should be thicker than 2 mm so as not to be broken by impact damage. The present study shows the feasibility of using CFC as a capsule material for the ITER NAS.     

基于活化法及MCNP程序的临界装置功率刻度

介绍了临界装置功率刻度的方法,在不同功率台阶下利用活化法测量临界装置的中子注量率分布及归一点的绝对中子注量率,并利用经修改编译的MCNP程序对临界装置的中子注量率分布进行校核计算。基于中子注量率测量及计算结果通过裂变率法计算不同功率台阶下临界装置的功率,同时外推到堆芯最大热中子注量率为1×10⁸cm^-2•s^-1时的功率,实现了临界装置的功率刻度。     

一体化总中子探测仪的研制

研制的一体化总中子探测仪将电子学部件小型化并集成于探测器顶部,与探测器组成一体,达到了体积小、移动方便的目的;用能转动方向的LED实时显示测量结果,通过计算机进行数据处理和报警显示;探头部分设计为具有一定的探测方向性。该探测仪可用于核视察及在车间、仓库进行长期监测,也可用于寻找在设备或核废物中能发射中子的核材料。仪器对前方相距10cm处的252Cf中子源的探测效率为0.92%。经过长期试用考验,总中子探测仪稳定可靠。     

多时空通道中子注量率密度数据采集系统方案设计

介绍了用在加速器驱动核能系统(ADS)次临界原理验证装置上的微机化多时空通道中子注量率密度数据采集系统设计方案．该数据采集系统用于采集多个空间位置的中子注量率密度水平随时间变化的数据。     

Long-lived neutron-induced radioisotopes in OKTAVIAN facility concrete wall after 38 year-operation

An intense 14 MeV neutron source facility named OKTAVIAN was installed in the A15 building,Osaka University in 1981.Along the operation period,new radioisotopes with various half-life have been produced as neutron activation products in its concrete wall shield.In this work,we investigated the concrete wall in the heavy irradiation room of OKTAVIAN using gamma spectrometry method to discover the presence of radioisotope having large half-life value (long-lived radioisotope) as neutron activation products.Computational simulations were performed prior to measurement to predict the presence of long-lived radioisotopes by employing MCNP5 and FISPACT codes.A pre-calibrated Germanium detector with high energy resolution was employed to measure the concrete.Several long-lived activation products have been observed such as ¹⁵²Eu,⁵⁴Mn,⁶⁵Zn,²²Na and ⁶⁰Co.The activity of each radioisotope was derived after estimating the detector efficiency using MCNP5.As a result of the measurement and analysis,the followings are concluded:(1) Though presence of activation products represents radiological risk to everyone who performs an experimental activity in the irradiation room of the OKTAVIAN facility,the present result shows that past experiments were carried out safely without any significant additional exposure dose coming from the wall for the last 38 years.(2) The approximated total fluence of D-T neutrons to the wall was successfully estimated from the produced radioisotope,¹⁵²Eu,because it has the longest half-life of 13.5 years among the observed radioisotopes.(3) From the results of (1) and (2),it could be possible to estimate the total activity of the concrete wall in the OKTAVIAN facility,which is very essential and important information,because this would be very valuable for decommissioning or disposal of the facility in the future.     

热中子照相成像系统的研制

成像系统是中子照相装置的关键组件之一.利用Gd和In金属研制了胶片静态照相转换屏,采用6LiF ZnS为转换材料,增强型CCD和制冷型CCD相结合,研制了CCD在线中子成像系统.