80.5 MeV/u碳离子诱发铜靶的放射性剩余产物测量

高能重带电粒子能直接穿透靶原子核外电子层,与原子核发生直接碰撞,发生散裂反应,产生一系列具有放射性的剩余产物核.重带电粒子诱发靶材放射性剩余核与辐射防护和人员安全有着密切联系,当前,大部分剩余核产额主要依靠蒙特卡罗粒子输运程序进行模拟计算,其准确程度亟需通过实验测量进行准确评估.本文利用能量为80.5 MeV/u的(12)^C⁶⁺粒子对薄铜靶开展了辐照实验与伽玛射线测量,结合伽玛谱学分析方法,得出了辐照产生的18种放射性剩余产物的初始活度和产生截面值,并与PHITS模拟结果进行对比.结果表明,PHITS模拟程序对放射性剩余核种类的估计具有较高可靠性,在其绝对产额方面,与实验测量仍具有较大偏差.     

Be(d,n)反应中子源能谱测量及应用

 利用中子飞行时间技术和BC501A液体闪烁探测器的粒子分辨特性,测量了0°方向、20 MeV氘束轰击厚金属铍靶反应产生的中子源能谱,测量的中子能谱范围为0.7～25.0 MeV。在60°方向放置芪晶体闪烁探测器,由刻度好的BC501A液体闪烁探测器归一校正后,用于中子源强度监测。利用Be(d, n) 反应中子源,采用单粒子灵敏度标定方法,实验标定了0.75~15.75 MeV能量范围内的薄膜闪烁探测器中子能量响应曲线,实验结果与蒙特卡罗模拟计算结果在8%的不确定度范围内一致。     

Determination of the time resolution for neutron scintillation detectors by multi-coincidence measurement

Based on the multi-coincidence measurement, the time resolution of three liquid scintillation detectors (BC501A) were determined strictly by solving the coincidence equations, where the influence from electronics estimated by self coincidence measurement as well as the background had been considered. The result of this work agreed well with the result that was deduced from the traditional method, and it will be helpful to analyze the energy resolution of neutron time of flight spectra measured by using such detectors at CIAE (China Institute of Atomic Energy).     

锂玻璃探测器中子探测效率的刻度

为了精确测量keV能区的中子俘获截面,中国原子能科学研究院正在建造一台4π 全吸收型γ 探测装置---GTAF,锂玻璃探测器将会作为中子束流监视器测量中子能谱。利用5SDH-2 加速器刻度了锂玻璃探测器在两个入射中子单能点(250 和565 keV) 的探测效率,并使用EANT4 和MCNP 程序模拟计算了锂玻璃探测器的相对探测效率。通过归一化实验数据和模拟结果,得到了锂玻璃探测器在10keV~1 MeV 能区的中子探测效率曲线。对于把锂玻璃探测器测量得到的飞行时间谱转化为中子束流能谱,是一项非常重要的工作,同时为探测器效率刻度提供了新方法。In order to accurately measure the neutron capture cross section in the energy range of keVMeV, 4 πgamma-ray total absorption facility (GTAF) is being constructed at China Institute of Atomic Energy (CIAE). The lithium glass detector will be used as a neutron beam monitor for GTAF. The detection efficiency of the lithium glass detector at two incident neutron energy points (250, 565 keV) was calibrated in 5SDH-2 accelerator, and the relative detection efficiency was simulated by GEANT4 and MCNP code. By the normalization of the experimental data and simulation result, the neutron detection efficiency curve of the lithium glass detector between 10 keV and 1 MeV was obtained. This work will be important to convert the Time-of-flight spectrum that be measured by Li-glass detector to the energy spectrum of neutron beam, and provide the new method for calibration of detection efficiency.     

Development of a facility for research of charged particle emission induced by fast neutron reactions

A facility has been constructed for research of charged particle emission     

不同厚度镥样品中子俘获反应实验研究

C₆D₆闪烁体探测系统结合脉冲权重技术被广泛应用于中子俘获反应截面测量研究.实验中采用的样品厚度直接影响中子束流时间,同时也影响实验数据的可靠性.本文基于中国散裂中子源反角白光束线(CSNS Back-n)C₆D₆探测系统,对比研究了不同厚度的镥(Lu)样品中子俘获反应截面的实验测量.利用GEANT4蒙特卡罗程序模拟了考虑样品厚度的探测系统光响应,计算出精确的脉冲权重函数.实验中,通过采用较长中子飞行距离和本底测量,得到了高精度的共振区产额分布.通过R矩阵理论分析产额分布,得到了相应的实验共振参数.结果发现,较厚Lu样品因其厚度效应导致共振曲线发生变化,实验共振参数与ENDF/B-Ⅷ.0评价数据库差距较大;然而,较薄Lu样品实验结果能够很好地再现ENDF/B-Ⅷ.0评价数据.     

A study of antineutrino spectra from spent nuclear fuel at Daya Bay

The Daya Bay Reactor Antineutrino Experiment is designed to determine the as yet unknown neutrino mixing angle, θ₁₃, by measuring the disappearance of electron antineutrinos from several nuclear reactor cores. The projected sensitivity in sin²(2θ₁₃) of better than 0.01 at a 90% CL should be achieved after three years of data-taking. Antineutrinos emitted from spent nuclear fuel (SNF) distort the soft part of the energy spectrum. In this article, a calculation of the antineutrino spectra from the long-life isotopes in SNF is performed. A non-equilibrium generation of long half-life isotopes during the running time of the reactor is also analyzed. Finally, we show that the antineutrino event rate contribution from SNF, which has been stored in the SNF pool for several years, may be non-negligible.     

中子引起氘核破裂反应的实验研究

对25 MeV中子引起氘核破裂反应的中子-中子准自由散射和17.36 MeV中子引起氘核破裂反应的中子-中子末态相互作用进行了细致的研究。首先,以小于5%的不确定度,精确测量了25MeV中子-中子准自由散射出射的中子三重微分截面。实验数据用基于现实核子-核子势(CD-Bonn,Argonne!18,Nijm I和II)的理论计算配合Monte-Carlo模拟进行了分析。实验结果比基于CD-Bonn势的理论预言高(16.0±4.6)%,进一步证实了目前的理论在中子-中子准自由散射方面还无法准确描述实验数据。其次,通过运动学非完全测量,精确测量了17.36 MeV中子引起氘核破裂反应在0°角附近出射的质子能谱,用基于现实核子-核子势(CD-Bonn、Bonn-B和Nijm I)的理论计算以及Monte-Carlo模拟分析了所测得的质子能谱,确定了中子-中子散射长度ann=(-16.8±0.6)fm。     

氘氚源中子穿过聚乙烯样品泄漏中子谱的测量与模拟

采用飞行时间技术测量了氘氚（D-T）源中子穿过不同厚度板状聚乙烯样品后40°方向的泄漏中子时间到达谱,样品的长和宽均为100 cm, 厚度分别为4.5, 9, 18和27 cm。 本底谱测量采用了无样本底测量和无样堵孔本底测量2种方案, 利用MCNP-4C程序模拟了相同实验条件下的泄漏中子时间到达谱, 模拟过程中考虑了源中子的能谱与角分布、脉冲中子束宽度、 探测器的效率以及样品的有效面积。通过比较发现, 采用无样测量谱作为本底时,计算值/实验值（C/E）值大于1, 并且随着样品厚度的增加而偏离1;而本底谱采用无样堵孔测量谱时, C/E小于1, 并且随着样品厚度的增加而接近1。通过对两套本底谱的分析, 并结合蒙特卡罗模拟, 计算求得了相应样品厚度下比较接近实际的本底谱,采用该模拟计算本底谱后,C/E值有了明显的改善。The neutron leakage spectrum were measured at 40° by time of flight method for polyethylene slabs with the thicknesses of 4.5, 9,18 and 27 cm,respectively. The experimental results were compared with the MCNP-4C simulations, which carefully considered many effects, such as the angle and energy distributions of the source neutrons,the width of the beam pulse,the detection efficiency and the effective measured area. The sample out and collimator filled spectra were measured as the background, and the results showed that C/E values were larger than 1 when using the sample out background spectra,but smaller than 1 when using the collimator filled background spectra. Combine these two different background spectra, a new method was used to calculate the background spectrum,and the results have a better agreement with the simulations.     

Measurement of the neutron spectrum of a Pu-C source with a liquid scintillator

The neutron response function for a BC501A liquid scintillator （LS） has been measured using a series of monoenergetic neutrons produced by the p-T reaction. The proton energies were chosen such as to produce neutrons in the energy range of 1 to 20 MeV. The principles of the technique of unfolding a neutron energy spectrum by using the measured neutron response function and the measured Pulse Height （PH） spectrum is briefly described. The PH spectrum of neutrons from the Pu-C source, which will be used for the calibration of the reactor antineutrino detectors for the Daya Bay neutrino experiment, was measured and analyzed to get the neutron energy spectrum. Simultaneously the neutron energy spectrum of an Am-Be source was measured and compared with other measurements as a check of the result for the Pu-C source. Finally, an error analysis and a discussion of the results are given.