100 MeV回旋加速器的高功率质子束流线研制

为调试100 MeV回旋加速器高功率束流及放射性同位素研制,设计了一条高功率质子束流线及可插拔式高功率束流调试靶。研究了100 MeV回旋加速器引出区色散效应及剥离膜的散射效应,从而优化了光学模拟的初始参数,使得模拟结果更加精确。高功率束流调试靶设计为可插拔式以代替常用固定式调试靶,该靶插入束流管道中时可进行高功率质子束流调试,在拔出时,质子束流可直接轰击束流线终端的靶站以生产放射性同位素。优化了高功率束流调试靶的水冷结构,确保调试靶可承受500 μA以上的质子束流。经调试,该束流线可传输最高流强520 μA的质子束流。     

扫描式质子束剂量分布成像仪的研制及性能分析

在重离子癌症治疗技术中,保证重离子束的质量（均匀性、束斑大小和位置、能量等）非常重要。为满足临床对重离子束质量的要求,本文设计了一种新型质子束剂量分布成像仪。该剂量分布成像仪基于闪烁屏、镜面反射屏与光学信号采集装置,将重离子束通过硫氧化钆闪烁屏转化为可见光,通过采集可见光信号,对重离子束予以质量控制。同时通过精密的电动位移平台对闪烁屏、镜面反射屏与光学信号采集装置的相对位置进行遥控从而调整设备视野。结果表明,该剂量分布成像仪在布拉格峰后沿的能量分辨率为0.22 mm等效水深,空间分辨率为0.35 mm,对单一光源响应的均匀性在图像视野中心10 cm×10 cm的区域内为±3.5%,并可通过算法对测量结果进行修正。该剂量分布成像仪能完成对重离子束质量的各项关键指标的测试,可用于医用质子束的质量控制。     

基于100 MeV紧凑型强流质子回旋加速器的束流切割器研制

通过理论分析和仿真模拟对中国原子能科学研究院一台100 MeV强流质子回旋加速器的束流切割器进行了优化设计,并同时研制出两套束流切割器进行实测对比,选定最佳方案。该切割器波形选择为回旋加速器高频频率的16分频28 MHz正弦波,具有结构紧凑体积小、螺旋谐振器Q相对较高、加载切割电压较高且功率损耗低、无需水冷等特点,同时配套研制了一套开口形状为正方形的选束狭缝装置。最后在实验终端成功获得了能量为100 MeV、重复频率为56 MHz的脉冲质子束。该切束器的成功研制不仅满足了核数据测量的应用需求,还极大地推动了回旋加速器束流脉冲化技术的发展。     

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。     

Development of Impregnated Agglomerate Pelletization (IAP) process for fabrication of (Th,U)O2 mixed oxide pellets

Impregnated Agglomerate Pelletization (IAP) technique has been developed at Advanced Fuel Fabrication Facility (AFFF), BARC, Tarapur, for manufacturing (Th,²³³U)O₂ mixed oxide fuel pellets, which are remotely fabricated in hot cell or shielded glove box facilities to reduce man-rem problem associated with ²³²U daughter radionuclides. This technique is being investigated to fabricate the fuel for Indian Advanced Heavy Water Reactor (AHWR). In the IAP process, ThO₂ is converted to free flowing spheroids by powder extrusion route in an unshielded facility which are then coated with uranyl nitrate solution in a shielded facility. The dried coated agglomerate is finally compacted and then sintered in oxidizing/reducing atmosphere to obtain high density (Th,U)O₂ pellets. In this study, fabrication of (Th,U)O₂ mixed oxide pellets containing 3–5 wt.% UO₂ was carried out by IAP process. The pellets obtained were characterized using optical microscopy, XRD and alpha autoradiography. The results obtained were compared with the results for the pellets fabricated by other routes such as Coated Agglomerate Pelletization (CAP) and Powder Oxide Pelletization (POP) route.     

基于光纤信号传输的核电磁脉冲场探测仪的设计与实现

介绍了基于光纤信号传输的核电磁脉冲场探测仪的原理、设计研制及达到的技术性能指标。采用快速傅里叶变换技术,对核电磁脉冲信号进行频谱截断分析,确定核电磁脉冲测量所需的最小带宽,在此基础上设计了激光器电路、探测器电路。核电磁脉冲场探测仪的研制对核电磁脉冲场的防护技术研究提供了器材保障,对提高我国电子信息设备核电磁脉冲场的防护研究水平具有重要意义。     

2020年中国核能发展战略研究

通过对中国核电发展面临形势的分析,强调了核电发展战略是我国电力发展战略和国家能源安全战略的重要组成部分,但加快核能发展面临诸多挑战。重点研究了核电发展的铀资源需求与资源供应保证能力、放射性废物处理处置等问题,以及中国核电发展面临的其他主要问题。阐述了2020年中国核能发展战略,并提出了有关措施建议。     

Effects of total-dose irradiation on gate-all-around (GAA) devices

The response of gate-all-around (GAA) MOS transistors to dose irradiation is quite different from that observed on other types of silicon-on-insulator (SOI) MOSFETs. In regular SOI MOSFETs, edge leakage increases substantially faster than the main transistor leakage upon creation of oxide charges due to the irradiation. The GAA MOSFET behaves in the opposite way; the shift of edge threshold voltage upon creation of charges in the oxide is smaller than that of the main transistor. As a result, a kink develops in the subthreshold characteristics of regular SOI MOSFETs upon irradiation, while the original subthreshold kink of GAA devices disappears when the device is irradiated     

在束流输运网络中强流离子束的复杂性及其控制研究进展

讨论了在束流输运网络中强流离子束在国防与民用等许多方面极其重要的应用潜力和诱人的发展前景。指出在束流输运网络中强流离子束形成的束晕-混沌的复杂性已经成为强流离子束应用中的关键问题之一;必须深入研究这类束晕-混沌的复杂特性及其产生的物理机制,并实现对束晕-混沌的有效控制。考虑到这是一个特殊的复杂的时空混沌的控制问题,解决这一难题已经成为强流离子束涉及的高科技领域、非线性-复杂性科学及复杂网络交叉领域中极富挑战性的一个新课题。最后,对上述课题当前的最新进展进行了评论,指出了该课题今后的研究方向。     

Development of Migration Prediction System (MIGSTEM) for Cationic Species of Radionuclides through Soil Layers

The migration prediction system (MIGSTEM) has been developed for estimating the migration of cationic species of radionuclides through soil layers systematically. The MIGSTEM consists of the migration experiments, the one-dimensional fitting code (inverse analysis code) for determining retardation factor and dispersivity (migration factors) and the three-dimensional differential code (prediction code) for estimating the migration of the radionuclides. The migration experiments are carried out for obtaining the concentration profiles of the radionuclides in unsaturated and saturated soil layers. Using the inverse analysis code, the migration factors are obtained at one time by fitting the concentration profiles calculated to those observed. The prediction code can give the contours of concentration and the one-dimensional concentration profiles at selected time, as well as the changing in the concentration at a selected position with time. The validity of the MIGSTEM was obtained by the benchmark test on the pre diction and inverse analysis codes. The MIGSTEM was applied to estimate the migration of Sr²⁺ through the sandy soil.     

基于虚拟仪器的CMOS器件脉冲总剂量效应在线测试系统研制

从效应研究的角度出发,利用Labview软件,自行研制了基于PCI插卡式虚拟仪器的CMOS器件脉冲总剂量效应在线测试系统,详细介绍了其硬件结构和软件设计思想,利用该系统在"强光一号"辐射模拟装置上开展了试验验证,表明其原理和技术途径是可行的,基本掌握了开展CMOS器件脉冲总剂量损伤以及时间关联退火响应研究的关键测试技术.     

Performance and Upgrade of the DAFNE Beam Test Facility (BTF)

The DAFNE Beam Test Facility (BTF) at the Frascati National Laboratory of INFN (LNF) has been operational since October 2002. This facility provides electron and positron beams with tunable energy from 25 MeV to 750 MeV, while the intensity can be varied from$10^10/ pulse$@ 0–50 Hz down to a single particle. In the last two years many experiments and beam tests have been hosted, so that the large use of the facility pushed the DAFNE staff to upgrade both the beam line, in order to improve the duty cycle, limited by frequent beam injection in the DAFNE main rings, and the diagnostic devices. The beam characteristics, the user experience and their typical measurements, the diagnostic tools developed and the available equipment are presented. Finally, we report on the facility upgrade and on operation in the new configuration.     

Development of an MCNP-tally based burnup code and validation through PWR benchmark exercises

The aim of this study is to evaluate the capabilities of a newly developed burnup code called BUCAL1. The code provides the full capabilities of the Monte Carlo code MCNP5, through the use of the MCNP tally information. BUCAL1 uses the fourth order Runge Kutta method with the predictor–corrector approach as the integration method to determine the fuel composition at a desired burnup step. Validation of BUCAL1 was done by code vs. code comparison. Results of two different kinds of codes are employed. The first one is CASMO-4, a deterministic multi-group two-dimensional transport code. The second kind is MCODE and MOCUP, a link MCNP–ORIGEN codes. These codes use different burnup algorithms to solve the depletion equations system. Eigenvalue and isotope concentrations were compared for two PWR uranium and thorium benchmark exercises at cold (300 K) and hot (900 K) conditions, respectively. The eigenvalue comparison between BUCAL1 and the aforementioned two kinds of codes shows a good prediction of the systems’ k-inf values during the entire burnup history, and the maximum difference is within 2%. The differences between the BUCAL1 isotope concentrations and the predictions of CASMO-4, MCODE and MOCUP are generally better, and only for a few sets of isotopes these differences exceed 10%.     

Superpowerful Linear Proton Accelerators for Neutron Generators and Electoronuclear Setups (review of projects)

Suggestions for superpowerful linear accelerators for electronuclear setups and high-intensity neutron generators are reviewed. The most important technical solutions, the characteristic features, and the state of the projects for linear accelerators with average accelerated beam power from 1 to 100 MW are examined: APT, SNS, JAERI/KEK, TRISPAL, TRASCO, ESS, KOMAC, Energy Amplifier, IFMIF, joint proposal by the Institute of Theoretical and Experimental Physcis, the Moscow Radio Electronics Institute, the Institute for High-Energy Physics, and other nuclear centers. 8 figures, 3 tables, 74 references.     

Sol-gel extrusion process for fabrication of (Th,U)O2 recycle fuel

An extrusion process based on sol-gel derived paste has been developed for the production of thoria recycle fuel as an alternative to the conventional powder-compaction/sintered-pellet route. Crack-free, high-density (9.7 Mg/m³) extruded slugs have been fabricated from sol-gel pastes prepared from ThO₂ powder (denitrated at 600°C) having a moisture content of ~ 16%, and mixed with phenolic resin. The extruded slugs were finally sintered at 1600°C. The effects of thorium-nitrate denitration temperature and organic binder addition on the quality of the fuel slugs are discussed in the paper.     

医疗器械辐射灭菌的现状及进展

本文叙述了医疗器械辐射灭菌的特点和在国内外的发展概况。论述了医疗器械辐射灭菌的几个关键问题：建立现代化的工业辐射灭菌工厂；建立完善的剂量监测系统；灭菌剂量的设定与验证；灭菌工艺的确认；日常加工的过程控制；网络管理和防伪标识；质量体系的认证和建设；辐射防护和安全等。同时提出了我国的医疗器械辐射灭菌事业在当前和今后一个时期内应关注的几个关键问题：机遇与发展；质量体系建设与国际水平接轨；现代企业制度的建设等。     

Progress of Beijing Radioactive Ion Beam Facility Isotope Separator On-line(BRISOL)

正Many of the reactions fundamentally important in nuclear physics and astrophysics are inaccessible to experimental study using stable-beam/stable-target combinations and therefore can only     

基于离散纵标输运计算方法的三维燃耗程序发展研究

为了精确描述和分析具有强烈各向异性中子注量率空间分布的反应堆燃耗过程,本文实现了三维SN 输运计算与燃耗计算的耦合,发展了相应的三维输运燃耗耦合计算程序.该程序系统采用接口程序自动耦合三维SN输运计算程序和同位素燃耗计算程序的方法实现对三维中子学计算模型的精细燃耗计算,获得燃料同位素成分、燃耗反应性、中子注量率空间分布等参数随燃耗时间的变化量.采用IAEA 基准校核例题对程序系统进行了校核,计算结果初步证明了所开发的三维燃耗程序系统的正确性.     

Measurement of Elastic Scattering of Proton Drilrline Nuclear System ~(17) F+~(58)Ni at Near Barrier Energy

<正>The reaction mechanisms of proton-rich nuclear systems have been attracted great attention nowadays.In the present work,the elastic scattering of the proton drip-line nuclear system~(17)F+~(58)Ni were measured,to investigate the influence of the proton-valence structure.