基于BF3正比管的宽量程脉冲中子探测技术

介绍了一种基于BF3正比计数管的宽量程脉冲中子探测技术。该技术采用多通道、组合式的BF3管阵列中子探测器组,以适应产额变化范围较宽的脉冲中子测试场合,并同时兼顾测量下限。基于该技术研制了一套BF3阵列中子探测系统并应用于脉冲中子源的测试,实验结果表明,该系统的脉冲中子测量范围可达5个数量级(56~8106),测量下限低、输出信号清晰,证明了该技术的可行性和有效性。     

神光Ⅲ主机装置首次间接驱动内爆集成实验

基于新建成的神光Ⅲ主机装置开展了首次激光间接驱动内爆集成实验。国内首次采用多环脉冲整形激光注入黑腔产生X光辐射驱动内爆,通过优化激光打靶参数控制驱动不对称性,演示了以惯性压缩为主、收缩比约15倍的DT靶丸内爆实验能力, 实现了准一维的高静产额(YOC)和高中子产额的物理指标;其中,真空黑腔DT靶丸最高中子产额为1.91012,YOC达到60%;充气黑腔DT靶丸最高中子产额为2.41012,YOC大约70%。该实验为未来开展多台阶整形辐射驱动、更高倍数收缩比的高压缩内爆综合实验、验证点火靶物理设计和关键调控措施有效性奠定了基础。     

SILEX-I装置上激光-团簇聚变实验中子产额测量

 超短超强脉冲激光与CD4团簇相互作用可以产生高能量的氘离子,从而产生DD聚变中子,这种团簇聚变中子源有着非常广阔的应用前景。在SILEX-I 100 TW飞秒激光装置上,超短超强脉冲激光与CD₄团簇相互作用实现了DD核聚变。团簇聚变的中子产额是实验中最为重要的物理量,在实验中采用高灵敏的中子探测器对团簇聚变产生的中子进行了测量,在现有实验条件下测得中子产额为10³。     

中子管非中子产物性质

采用两只经过标定的ST401闪烁探测器,测量了脉冲中子管的中子产额,在其中一只探测器前端增加铅板屏蔽,1 cm的铅屏蔽使探测器输出减少了18.20%,在加速器中子源上进行的类似实验表明,0.5 cm的铅使探测器的输出减少了2.90%。对两个中子源上测量的情况进行了蒙特卡罗模拟,加速器实验与模拟符合较好,脉冲中子管实验差别较大。对实验和模拟的情况进行了分析,结果表明:中子管除产生中子外,还会产生数量较多的轫致辐射X射线,这些X射线对准确测量中子管中子产额将造成不良影响。     

神光Ⅱ升级装置锥壳靶间接驱动快点火集成实验

在神光Ⅱ升级装置上完成了国际上首次间接驱动快点火集成实验。实验采用双台阶脉冲整形激光注入黑腔产生X射线准等熵压缩锥壳靶,实现了高密度压缩,然后采用皮秒超短脉冲激光注入加热燃料。实验中观测到中子产额由皮秒激光注入前的5×103增加到2.2×105,中子产额增益达到44倍,实验证实了皮秒激光具有明显燃料加热效果。该实验为进一步开展快点火热斑形成效率和相关物理研究奠定了基础。     

厚靶D（d,n）^3He反应加速器中子源的产额、能谱和角分布

给出一种计算氘钛厚靶D(d,n)3He反应加速器中子源的产额、能谱和角分布的方法,并发展了一个计算机模拟程序,程序能够计算氘束流能量小于1.0 MeV的中子源的产额、能谱和角分布.计算时使用推荐的D(d,n)3He反应截面数据和来自SRIM-2003程序的氘在氘钛靶中的阻止本领数据.给出一些典型计算结果,包括中子积分产额、中子能谱和角分布.     

DT聚变脉冲中子产额的活化测量法

设计了一个测量高强度DT聚变脉冲中子产额的活化探测器.该探测器由中子慢化体、天然银片、塑料闪烁体和光电倍增管组成,其输出电流通过一个小电流计来获取.通过分析探测器在直流标定和脉冲测量两种状态下输出电流的变化曲线,求解出了特征参数,进而推导计算出DT聚变脉冲中子源的产额.实践证明,这种测量方法与传统的活化法相比,减少了对...     

液体闪烁体探测器测量皮秒激光脉冲中子源能谱

在星光Ⅲ实验装置上开展皮秒激光脉冲中子源实验,使用液体闪烁体探测器测得较好的中子信号,利用飞行时间法获得中子的能量/时间分布,通过示波器电压时间积分与阻抗之比得到不同能量段的电荷值。建立液体闪烁体探测器Geant4计算模型,通过实际打靶情况与标定情况下液体闪烁体探测器出光口收集到的可见光光子数之比,结合标定的灵敏度数据,获得液体闪烁体探测器对不同能量中子的灵敏度。计算得到源发射的中子能谱,能量在1 MeV以上的液体闪烁体探测器方向测得的中子产额为1.04108 sr-1。     

高效率BF3正比探测器阵列探测中子技术

针对中子产额范围宽、下限低，研制4个具有高中子探测效率的正比探测器，由置于慢化体内的BF3正比计数管阵列和电压前置放大器组成。每个探测器内共包括12支BF3正比计数管，并根据不同的数目分为两组。在图l所示的实验中，利用这种多管的正比探测器，可以对产额变化范围宽、下限低的不同脉冲中子源产额进行测量。     

拍瓦激光与铜靶作用产生光核中子的数值模拟研究

激光驱动中子源由于中子通量高、短脉冲等特点受到广泛关注。通过辐射流体动力学、粒子动力学和蒙特卡罗三种数值模拟程序的组合使用,对超短强激光与铜靶作用产生光核中子进行了全物理过程模拟。首先使用辐射流体动力学程序获得激光预脉冲产生的预等离子体密度分布,然后将预等离子体输入粒子动力学程序获得超短强激光主脉冲产生的超热电子信息,最后将超热电子输入蒙特卡罗程序得到光核中子。模拟获得了光核中子的产额、能谱和角分布信息,发现采用强度1022 W/cm2激光、直径和厚度均为4 cm的Cu圆柱靶,可以获得产额为1.2108/J的光核中子。     

Triton and alpha-particle contribution from LiF converter for neutron dosimeter

A personnel neutron dosimeter prototype based on chemical and electrochemical etched CR-39 detector, combined with LiF converter, has been calibrated using an ICRP-like phantom, under a heavy-water moderated Californium source neutron spectra; A conversion factor of 1.052±126 spots cm⁻² mSv⁻¹ was obtained. The sealing properties of the detector holder showed a ten-fold reduction in radon background when it was tested in a high radon atmosphere. A convenient mechanical shock resistance was achieved in LiF converters by sintering to 11 tons pressure LiF powder at 650°C, during one hour.     

基于小型加速器的编码中子源成像研究

编码中子源成像可以在对中子注量率影响不大的情况下大大提高成像的准直比, 从而提高成像质量.北京大学开展了基于小型加速器的编码中子源成像技术研究工作. 不同于已有的基于反应堆的小面积编码板的研究工作, 北京大学建立了基于小型加速器的大面积编码板的编码中子源成像实验平台, 并对加速器中子源上的实验方法和数据处理进行了探索, 对比了重建算法, 获得了初步的重建照片.研究工作表明, 编码中子源成像技术可用于加速器中子源, 但重建图像质量仍须提高. 关键词： 加速器中子源 中子成像 编码源成像 图像重建     

High-Resolution Neutron Diffractometer Based on the IN-06 Pulsed Neutron Source at the Institute for Nuclear Research,Russian Academy of Sciences

A high-resolution neutron diffractometer has been fabricated on the basis of an IN-06 pulsed neutron source at the Institute for Nuclear Research, Russian Academy of Sciences. The diffractometer incorporates two blocks of detectors with helium neutron counters and time-of-flight (TOF) focusing at scattering angles of 156°–165°. A block of new-type high-efficiency scintillation detectors of thermal neutrons based on a ZnS(Ag)/LiF scintillator and silicon photomultipliers with TOF focusing is developed and tested. Test measurements are performed, and the diffractometer resolution is estimated. The diffraction pattern of nonmagnetic NiCrAl alloy is measured and used to determine the phase composition by means of the Rietveld method. It is demonstrated that the given setup can be applied to phase analysis.     

Neutron dosimetric measurements in shuttle and MIR

Detector packages consisting of thermoluminescence detectors (TLD), nuclear emulsions and plastic track detectors were exposed at identical positions inside MIR space station and on shuttle flights inside Spacelab and Spacehab during different phases of the solar cycle. The objectives of the investigations are to provide data on charge and energy spectra of heavy ions, and the contribution of events with low-energy deposit (protons, electrons, gamma, etc.) to the dose, as well as the contribution of secondaries, such as nuclear disintegration stars and neutrons. For neutron dosimetry 6LiF (TLD600) and 7LiF (TLD700) chips were used both of which have almost the same response to gamma rays but different response to neutrons. Neutrons in space are produced mainly in evaporation and knock-on processes with energies mainly of 1-10 MeV and up to several 100 MeV, respectively. The energy spectrum undergoes continuous changes toward greater depth in the attenuating material until an equilibrium is reached. In equilibrium, the spectrum is a wide continuum extending down to thermal energies to which the 6LiF is sensitive. Based on the difference of absorbed doses in the 6LiF and 7LiF chips, thermal neutron fluxes from 1 to 2.3 cm-2 s-1 are calculated using the assumption that the maximum induced dose in TLD600 for 1 neutron cm-2 is 1.6 x 10(-10) Gy (Horowitz and Freeman, Nucl. Instr. and Meth. 157 (1978) 393). It is assumed that the flux of high-energy neutrons is at least of that quantity. Tissue doses were calculated taking as a mean ambient absorbed dose per neutron 6 x10(-12) Gy cm2 (for a10 MeV neutron). The neutron equivalent doses for the above-mentioned fluxes are 52 micro Gy d-1 and 120 micro Gy d-1. In recent experiments, a personal neutron dosimeter was integrated into the dosimeter packages. First results of this dosimeter which is based on nuclear track detectors with converter foils are reported. For future measurements, a scintillator counter with anticoincidence logic is under development.     

基于3.5 MeV射频四极质子加速器硼中子俘获治疗装置的束流整形体设计

在硼中子俘获治疗(BNCT)装置中,束流整形体(BSA)的作用是将中子源产生的快中子束流慢化至超热中子能区(0.5 eVE10 keV),并尽可能减弱快中子、热中子和γ射线的成分,同时保证中子的方向性,其设计与优化是BNCT装置设计工作的核心内容之一.本文采用3.5 MeV,10 mA的质子束轰击锂靶,由核反应~7Li(p,n)~7Be产生的中子为源项,针对BSA的慢化体材料和结构、γ屏蔽层和热中子吸收层的厚度等参数进行蒙特卡罗模拟设计与优化.研究发现,采用Fluental和LiF两种慢化材料间隔2 cm层状堆叠的三明治BSA构型,在保证快中子剂量成分(D_f/φ_(epi)),γ剂量成分(D_γ/φ_(epi))和热中子比例φ_(th)/φ_(epi)满足IAEA-TECDOC-1223报告推荐要求的同时,在BSA出口处超热中子注量率优于单独使用Fluental和单独使用LiF的BSA设计.BSA出口处修正的Synder人头几何模型中的剂量分布计算结果显示:上述三明治构型的深度剂量分布与单独使用Fluental材料构型的结果基本相当,优于单独使用LiF构型,表明Fluental和LiF层状堆叠的三明治BSA构型是一种可行的BSA结构.     

利用气泡探测器测量激光快中子

在利用超强激光驱动中子源的研究和应用研究中,中子源的产额及其角分布至关重要.我们在星光Ⅲ号激光装置上采用气泡探测器对强激光驱动的中子源的产额及其角分布进行了测量.利用超强皮秒激光与碳氘薄膜靶相互作用产生高能氘离子束撞击次级碳氘靶,通过氘-氘核反应产生准单能快中子.实验发现中子束的发射具有一定的方向性,在入射氘离子的传输方向上中子束具有更高的强度,测量得到的中子束最大强度为5.13×10⁷ n/sr.利用实验测量的氘离子能谱和角分布对中子束角分布进行了理论计算,结果与实验测量基本一致.     

Diagnostic technique for measuring fusion reaction rate for inertial confinement fusion experiments at Shen Guang-III prototype laser facility

A study is conducted using a two-dimensional simulation program(Lared-s)with the goal of developing a technique to evaluate the effect of Rayleigh–Taylor growth in a neutron fusion reaction region.Two peaks of fusion reaction rate are simulated by using a two-dimensional simulation program(Lared-s)and confirmed by the experimental results.A neutron temporal diagnostic(NTD)system is developed with a high temporal resolution of~30 ps at the Shen Guang-III(SG-III)prototype laser facility in China,to measure the fusion reaction rate history.With the shape of neutron reaction rate curve and the spherical harmonic function in this paper,the degree of Rayleigh–Taylor growth and the main source of the neutron yield in our experiment can be estimated qualitatively.This technique,including the diagnostic system and the simulation program,may provide important information for obtaining a higher neutron yield in implosion experiments of inertial confinement fusion.     

氘代乙烷团簇库仑爆炸产生高能氘核和中子的研究

采用简化库仑爆炸模型对强激光脉冲照射氘代乙烷团簇发生的库仑爆炸过程进行数值模拟,研究了氘代乙烷团簇爆炸产生的氘核动能、中子产额与团簇尺寸的关系,且与氘代甲烷团簇产生的氘核动能及中子产额进行了比较.研究表明,尺寸为5 nm的氘代乙烷团簇在发生库仑爆炸后氘核的最大动能为20.96 keV,获得的中子产额为6.31×105,比同尺寸氘代甲烷团簇产生的氘核最大动能及中子产额更大.因此相对于氘代甲烷团簇,大尺寸的氘代乙烷团簇更适合作为激光驱动团簇库仑爆炸获得高额中子的靶材,这与报道的实验推论相一致.     

Generation of nanosecond neutron pulses in vacuum accelerating tubes

The generation of neutron pulses with a duration of 1–100 ns using small vacuum accelerating tubes is considered. Two physical models of acceleration of short deuteron bunches in pulse neutron generators are described. The dependences of an instantaneous neutron flux in accelerating tubes on the parameters of pulse neutron generators are obtained using computer simulation. The results of experimental investigation of short-pulse neutron generators based on the accelerating tube with a vacuum-arc deuteron source, connected in the circuit with a discharge peaker, and an accelerating tube with a laser deuteron source, connected according to the Arkad’ev-Marx circuit, are given. In the experiments, the neutron yield per pulse reached 107 for a pulse duration of 10–100 ns. The resultant experimental data are in satisfactory agreement with the results of computer simulation.     

用于位置灵敏型中子探测器的6LiF/ZnS（Ag）闪烁体性能研究

研究了掺杂6LiF的ZnS(Ag)闪烁体对中子、γ射线的发光特性和EJ426闪烁体样品的热中子探测效率、出射光产额和γ灵敏度。EJ426的热中子探测效率为32.4%,出射光产额为8.01×103光子/中子,70 mV阈值时的γ灵敏度小于10-7,表明EJ426是较理想的闪烁体型位置灵敏中子探测器材料。