The Progress of a Microbeam Facility in the Institute of Plasma Physics

The progress of a microbeam facility in the institute of Plasma Physics was discussed in this paper.This kind of equipment can supply single-particle beam which may be implanted into cells in micrometer-radius and measured by a new outstanding detector among global microbeam systems.Measurements by some plain targets showed that the highest current after the accelerator tube can be larger than 20μA ,the H2^ current before the second bending magnet is near 0.9μA ,the current after the second bending magnet is near 0.8μA,and the current of the beam line(after a 2-mm diameter aperture)is near 0.25nA which is enough for the single-particle microbeam experiment.It took scientists 3 months to do their microbeam experiment after setting up the qccelerator beam line and get the microbeam from this equipment.Two pre0collimators were installed between the 2-mm diameter aperture and the collimator to survey the beam.Tracks on the CR39 film ectched in the solution of NaOH showed that the beam can go through the collimator including a 10μm diameter aperture and the 3.5μm thick vacuum sealing film(Mylar).A new method,which is called optimization of the beam quality,was put forward in this paper,in order to get smaller diameter of beam-spot in microbeam system.     

Cell Locating with the Image Analysis System of the CAS-LIBB Single-Particle Microbeam Facility

A single-particle microbeam facility has been constructed at the Key Laboratory ofIon Beam Bioengineering (LIBB), Chinese Academy of Sciences (CAS). At the CAS-LIBB microbeam facility, we have developed protocols to place exact numbers of charged particles through nuclear centroids of cells, at defined positions in the cytoplasm relative to the nucleus, and through defined fractions of cells in a population. In this paper, we address the methods for nucleus, cytoplasm and bystander (either a single or an exact number of ions is delivered to a certain percentage of cells in a population to study the bystander effects of radiation) irradiation in detail from theprecision of target finding and cell locating in the image analysis system. Moreover, for cells touching slightly in an image, a watershed method is used to separate these touching objects;after that, the number of objects in an image is counted accurately and the irradiation points are located precisely.     

Automatic Thresholding in the Control Software of CAS-LIBB Microbeam Facility

In this paper, two automatically calculated thresholds based on a statistical analysis of the histogram were used to apply binary segmentation to the bitmap. When the CCD and the microscope have been properly configured and the raw image is preprocessed, the Otsu＇s method can meet the need of the control program on the whole.     

重离子微束装置中真空窗的研究

中国科学院近代物理研究所（IMP）正在兰州重离子加速器（HIRFL）系统中研制中能重离子微束终端,以对重离子进行准确定位和精确计数。应用有限元分析软件对不同结构、不同材料的真空窗进行受力分析,模拟真空窗的形变和等效应力,运用强度理论考察候选真空窗的安全性;运用SRIM程序模拟离子的小角散射、横向射程,详细计算入射离子的能量、真空窗材料和厚度及空气层对束斑展宽的影响;最后提出真空窗适宜的结构、材料及厚度范围。     

Dosimetric Analyses of Single Particle Microbeam in Cell Irradiation Experiment

Single particle microbeam （SPM） is uniquely capable of delivering precisely the predefined number of charged particles to determined individual cells or sub-cellular targets in situ. It has been recognized as a powerful technique for unveiling ionization irradiation mechanisms of organism. This article describes some investigations on the irradiation quality of SPM of major world laboratories by means of Monte Carlo method based on dosimetry and microdosimetry. Those parameters are helpful not only to improve SPM irradiating cell experiments but also to study the biological effects of cells irradiated by SPM.     

Single-Ion Microbeam for Applications in Radiobiology： State of the Art

Single-Ion Microbeam (SIM) is uniquely capable of precisely delivering a predefined number of charged particles (precise doses of radiation) to individual cells or sub-cellular targets in situ. Since the early 1990‘s, there has been an ever-increasing interest in developing and applying the SIM technique to problems in radiobiology for studies of cell and tissue damaged by ionizing radiations. Potential applications for SIM in radiobiology continues to grow and have been diversified. There are currently more than 14 SIM facilities worldwide, and they have been in a constant state of evolution. This paper reviews the current state of SIM research worldwide and the related pivotal technological developments in the fields of both biophysics and radiobiology. Representative applications and the perspective of SIM are also introduced and discussed.     

ADS"启明星"次临界实验平台物理方案初步设计

使用MCNP程序对几种堆芯均匀化布置进行了临界计算，keff在0．92～1．00之间。计算结果为加速器驱动的次临界系统(ADS)的次临界实验平台物理方案设计提供了初步设计方案。     

放射性核束首次物理实验的探测器系统

描述了放射性核束进行首次物理实验所使用的探测器系统的构成及各类探测器的性能,同时给出了该系统用于物理实验所得到的人令人满意的在线获取结果。     

借助CFD方法的燃料转运通道热工水力实验的台架设计

核电厂安全设计中,需要考虑燃料转运过程中的热工安全问题。具体而言,需要研究复杂几何结构内发生于狭窄水平流道的有加热源的自然循环流动传热过程。借助计算流体力学(CFD)方法,对流动传热过程进行了预研,并据此选定了重点研究区域和关键物理现象。结合实验需求,设计了专用的热工水力实验台架,并根据相似理论分析了实验段与原型之间的差异,以及由此引入的误差,为开展进一步的实验研究奠定了基础。     

闪烁光纤及其在粒子物理实验中的应用

本文简述了闪烁光纤的基本特性,并介绍了目前在粒子物理中的应用研究。     

等离子体参数对中性束注入下快离子自举电流影响

本文数值研究了等离子体参数对大纵横比托卡马克装置中性束注入时产生的快离子净电流密度分布的影响。研究表明净电流密度的大小随背景等离子体温度的增大而增大,随等离子体密度的增大而减小,等离子体有效电荷对净电流密度的大小影响较小,但随有效电荷的增大净电流密度的峰值向等离子体边缘偏移。     

Control of Beam Energy and Flux Ratio in an Ion-Beam-Background Plasma System Produced in a Double Plasma Device

Plasmas containing ion beams have various applications both in plasma technology and in fundamental research. The ion beam energy and flux are the two factors characterizing the beam properties. Previous studies have not achieved the independent adjustment of these two parameters. In this paper, an ion-beam-background-plasma system was produced with hotcathode discharge in a double plasma device separated by two adjacent grids, with which the beam energy and flux ratio(the ratio between the beam flux and total ion flux) can be controlled independently. It is shown that the discharge voltage(i.e., voltage across the hot-cathode and anode) and the voltage drop between the two separation grids can be used to effectively control the beam energy while the flux ratio is not affected by these voltages. The flux ratio depends sensitively on hot-filaments heating current whose influence on the beam energy is relatively weak,and thus enabling approximate control of the flux ratio     

核设施实物保护技术探究

实物保护系统(PPS)是核工程技术领域中一个综合多学科的系统工程,包括探测、延迟、响应三大要素。系统介绍了实物保护系统(PPS)设计与分析的过程和方法以及实物保护系统网络集成,旨在通过采用先进的技术方法来提高实物保护系统的功能性、稳定性与可靠性,使其在保护核材料和核设施安全方面发挥更有效的作用。     

Preliminary design of the control and data acquisition systems for the Neutral Beam Test Facility

The Neutral Beam Test Facility, which will be built in Padova, Italy, is aimed at developing the ITER heating neutral beam injector (HNB) and at testing and optimizing its operation up to nominal performance before installation on ITER. It requires the development of two independent experiments referred to as SPIDER (source for production of ions of deuterium extracted from Rf plasma) and MITICA (megavolt ITer injector & concept advancement). SPIDER will explore the full-size negative ion source for ITER, whereas MITICA will explore the full-size ITER neutral beam injector. Both experiments will be designed for long-pulse operation, up to 3600 s, as ITER itself. MITICA includes three functional components: the heating neutral beam injector plant system (HNB), which is the device under test; the auxiliary plant system (AUX), which includes all equipment to operate the HNB in the test facility (e.g. the local electric grid to feed the HNB power supplies), and MITICA supervisory system that is an electronics/informatics infrastructure to operate the facility. The paper introduces the requirements for the control and data acquisition systems of the experiments and proposes a preliminary design for both systems. SPIDER, which is preparatory to MITICA and will be developed on a shorter time scale, has no constraints coming from ITER CODAC, whereas MITICA includes the ITER neutral beam injector and therefore must be fully compatible with ITER CODAC.     

MLFC在质子单粒子效应实验束流诊断中的应用

对宇航微电子器件进行抗质子辐射性能评估时,常利用加速器产生的质子束流来测量其质子单粒子效应截面曲线（σ-E曲线）。基于北京HI-13串列加速器重离子辐照装置,研制了适用于质子能量测量的多叶法拉第筒（MLFC）,为今后开展质子单粒子效应辐照实验奠定基础。测试结果表明,研制的MLFC既可测量质子能量和束流强度,也能测量质子束流的能量纯度,这对判定束流是否符合实验要求及调束非常实用。     

强流脉冲中性源的等离子体发生器电源

本文叙述了强流脉冲中性源等离子体发生器电源的特殊要求,给出了用于7×35cm~2大面积源的灯丝电源和弧流电源的主电路。     

Calculation of Beam Intensity Distribution for the Neutral Beam Injection in EAST

Theoretical beam intensity distribution is derived for the neutral-beam-injection ion source with a multi-slot extraction in EAST. The beam intensity profile, b...     

利用MCNPX模拟钴-60辐照装置研发样品吸收剂量的研究

本文采用高能粒子输运程序MCNPX2.5.0对钴-60辐照装置建立几何模型,对位于辐照室中垂直于双板源架中心点3 m处的研发样品的吸收剂量（率）进行模拟计算。根据实际生产,选择辐照室有或无辐照产品两种工况,一是分别模拟12种不同包装规格且不同质量研发样品在不同辐照时间的吸收剂量;二是模拟计算包装规格相同且质量不同的10种样品的吸收剂量率;三是模拟计算包装规格不同但质量相同的9种样品的吸收剂量率。结果表明,在辐照室有或无辐照产品两种工况下,后者的值比前者平均大4.19倍;三类研发样品的吸收剂量（率）及变化规律可以作为实际生产研发的参考。MCNPX理论模拟计算对于辐照新产品具有重要的实际指导意义。     

正电子致电离截面实验中束流强度的在线测量

本文采用HPGe探测器实时收集了正电子碰撞厚Ti靶伴随产生的湮灭光子,并结合HPGe探测器对放置在碰撞点处²²Na标准源产生的511 keV湮灭光子的探测效率刻度值,得到了8~9.5 keV正电子引起Ti原子内壳层电离截面实验中正电子束流强度的实时测量结果。结果表明,在实验测量的38 h内,基于²²Na标准源慢正电子束流装置产生的正电子束流强度不稳定,随时间的变化有着不同程度的衰减,且存在小幅度波动现象。因此,低能正电子致原子内壳层电离截面实验中应采用在线法获取慢正电子束流强度。     

Analysis of fuel management in the KIPT neutron source facility

Argonne National Laboratory (ANL) of USA and Kharkov Institute of Physics and Technology (KIPT) of Ukraine have been collaborating on the conceptual design development of an experimental neutron source facility consisting of an electron accelerator driven sub-critical assembly. The neutron source driving the sub-critical assembly is generated from the interaction of 100 KW electron beam with a natural uranium target. The sub-critical assembly surrounding the target is fueled with low enriched WWR-M2 type hexagonal fuel assemblies. The U-235 enrichment of the fuel material is <20%. The facility will be utilized for basic and applied research, producing medical isotopes, and training young specialists. With the 100 KW electron beam power, the total thermal power of the facility is ∼360 kW including the fission power of ∼260 kW. The burnup of the fissile materials and the buildup of fission products continuously reduce the system reactivity during the operation, decrease the neutron flux level, and consequently impact the facility performance. To preserve the neutron flux level during the operation, the fuel assemblies should be added and shuffled for compensating the lost reactivity caused by burnup. Beryllium reflector could also be utilized to increase the fuel life time in the sub-critical core. This paper studies the fuel cycles and shuffling schemes of the fuel assemblies of the sub-critical assembly to preserve the system reactivity and the neutron flux level during the operation.