铜活化法诊断神光Ⅲ主机装置氘氚中子产额

介绍了铜活化诊断氘氚中子产额的测量原理,分析了62 Cu和64 Cu两种活化核素在符合测量中的贡献。针对不同范围内的中子产额测量,提出了系统灵敏度相对标定法和64 Cu活化核标定法。通过添加中子屏蔽锥测量了标定场所散射中子影响。计算评估了63 Cu(n,γ)64 Cu反应过程对活化测量的影响。在神光Ⅲ主机装置上,利用该系统测量了直接驱动氘氚中子产额。实验结果表明:氘氚中子产额在109~1013范围采用相对标定方法较为合适,64 Cu活化核的标定方法适用于1012~1016范围内产额测量。标定场所散射中子对灵敏度标定因子影响约0.4%。63 Cu俘获辐射反应在64 Cu活化核标定中贡献小于1%。目前神光Ⅲ主机装置直接驱动氘氚中子产额约8×1012。     

An improved method of unfolding neutron TOF spectrum for low ion temperature inertial confinement fusion

The fuel ion temperature in inertial confinement fusion can be determined from the neutron energy spectrum. For the implosion experiment with low neutron yield, and thus low signal-to-noise ratio, a new technique to unfold the neutron energy spectrum from the observed neutron time-of-flight signal is presented in this paper. This method uses a low-pass filter to remove noise from the signal with a threshold value determined by power spectrum analysis. This technique has been applied to the analysis of the observed neutron time-of-flight signals in the indirect drive implosion experiment conducted on Shenguang III prototype laser facility, and fuel ion temperatures of about 1.0 keV are obtained.     

大型激光原型装置低燃料面密度诊断技术

由于某大型激光原型装置内爆实验的燃料面密度很低,提出了利用充纯D燃料内爆产生的初级DD中子和次级DT中子的产额比值来诊断燃料面密度的方法。在该原型装置的首轮内爆实验中,利用研制的高灵敏塑料闪烁体探测器对初级DD中子产额和次级DT中子产额进行了测量。通过实验发现,当初级DD中子产额高于108时,可以测得次级DT中子实验数据。建立了均匀内爆模型,用初级和次级中子产额比值法对燃料面密度进行计算,获得的该原型装置首轮内爆实验燃料压缩的平均面密度小于4.0 mg/cm2。     

ICF中子产额测量中统计涨落分析及计算

 塑料闪烁探测器通常用来测量氘氘、氘氚聚变中子产额。中子在闪烁体中产生的质子数的统计涨落及质子在闪烁体中沉积能量的统计涨落为测量结果引入了两项不确定度分量。以氘氚聚变中子为例,分析了这两种统计涨落的概率密度函数的计算方法,该计算方法也适用于其它能量的单能快中子和塑料闪烁体作用的相应计算。     

铟活化诊断氘氘中子产额不确定度分析

介绍了铟活化诊断氘氘中子产额的测量原理,分析了中子产额测量不确定度的来源及评定方法。中子产额测量不确定度主要由灵敏度标定不确定度、活化射线净计数不确定度、立体角测量不确定度及测量系统的随机误差等构成。评估了灵敏度标定过程中加速器中子与聚变中子能量差异、大厅散射中子本底等因素对灵敏度标定的影响,并评估了宇宙射线本底对活化射线净计数测量的影响。分析了中子产额处于不同量级时起主要作用的不确定度分量,提出了减小灵敏度标定不确定度的方法。以实验数据为基础,对具体的实验数据进行了分析计算。结果表明:利用伴随粒子法在加速器中子源上标定出铟活化测量系统灵敏度的相对标准不确定度为4.3%。中子产额低于1010时,产额测量不确定度大于7%,活化射线净计数误差是产额测量误差的主要来源;产额大于1010时,测量不确定度好于7%,中子产额测量不确定度主要由灵敏度标定不确定度引起。     

Uncertainties induced by statistical fluctuations in fast monoenergetic neutron yield measurements

A plastic scintillation detector was used to measure the yield of deuterium-deuterium (DD) neutrons or deuterium-tritium (DT) neutrons. Collisions of fast neutrons with hydrogen nucleus in a scintillator generated recoil protons, the energies of which were fully deposited in the scintillator. The statistical fluctuation of the protons' number and that of the protons' total energy were two sources of measurement uncertainty. Based on DT neutrons, this paper represents the algorithms of computing the probability density functions of the two sources. Uncertainties of the measurement induced by statistical fluctuations were finally computed by constructing the probability density functions of the proton number and that of the neutron number.     

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。     

An improved method of unfolding neutron TOF spectrum for low ion temperature inertial confinement fusion

The fuel ion temperature in inertial confinement fusion can be determined from the neutron energy spectrum. For the implosion experiment with low neutron yield, and thus low signal-to-noise ratio, a new technique to unfold the neutron energy spectrum from the observed neutron time-of-flight signal is presented in this paper. This method uses a low-pass filter to remove noise from the signal with a threshold value determined by power spectrum analysis. This technique has been applied to the analysis of the observed neutron time-of-flight signals in the indirect drive implosion experiment conducted on Shenguang Ⅲ prototype laser facility, and fuel ion temperatures of about 1.0 keV are obtained.     

13.5-14.6MeV中子能区锶同位素反应截面的测量

在13.5—14.6MeV中子能区用活化法测量了⁸⁴Sr(n, 2n)⁸³Sr,⁸⁶Sr(n, 2n)^85mSr, ⁸⁶Sr(n, 2n)⁸⁵Sr,⁸⁸Sr(n, 2n)^87mSr, ⁸⁴Sr(n, p)⁸⁴Rb, ⁸⁶Sr(n, p)⁸⁶Rb,⁸⁸Sr(n, p)⁸⁸Rb和⁸⁸Sr(n, α)^85mKr的 反应截面值, 以⁹³Nb(n, 2n)^92mNb反应截面为中子注量标准, 并且将测量值和收集到的文献值做了比较.