利用MCNPX模拟中子多重性脉冲序列采集

介绍了中子多重性测量分析方法的理论关系式以及中子脉冲序列的形成原理,并利用MCNPX与MATLAB程序模拟便携式中子符合探测器(PNCC)进行中子多重性测量,得到了铀材料的中子多重性分布,实现了中子脉冲序列的采集。实验研究验证了便携式中子符合探测器用于中子多重性测量的可行性。     

电流模式飞行时间中子能谱测量方法研究

中国散裂中子源在中子学性能调试期间需要发展快速的中子能谱测量系统,希望在一个或几个质子脉冲周期内获得中子能谱。本研究发展了一套高探测效率的电流模式飞行时间能谱测量系统,测量系统由锂玻璃探测器、NI-PXIe-5122数据采集卡、Lab VIEW数据采集控制软件、高压电源等组成。在绵阳研究堆极化中子反射谱仪中子束线上开展了电流模式飞行时间中子能谱测量系统测试,分别测量了中子能谱和中子通量。同时,利用脉冲计数模式飞行时间方法和金箔活化法分别测量了该中子束线的中子能谱和中子通量,将测得的数据与电流模式飞行时间中子能谱测量系统测量结果进行对比,验证了电流模式飞行时间方法测量中子能谱和中子通量的可靠性。     

含钚废物中钚总量NDA测量技术研究

<正>针对生产工艺特定时期内产生的废物中钚的总量,开展了NDA实验研究。主要包括涉及中子测量的实验装置改进设计和涉及钚同位素测量的γ能谱测量实验条件选择,后者包括标准样品测量。1)中子测量装置的改进设计根据测量对象,完成了中子测量装置的改进设计,以便于进行含钚废物的有源测量分析。中子测量分为无源中子测量和有源中子测量两种模     

中子剂量当量测量技术研究进展

中子剂量当量的测量,已在国民经济和国防科技中取得了广泛的应用。但在中子剂量当量测量过程中,由于探测器能量响应及不确定因素等的影响,中子剂量当量测量的准确度一直不高。论文介绍了中子剂量当量的测量方法,影响中子剂量当量测量的因素,并展望了中子剂量当量测量的发展方向。     

中子能谱快速测量

为了实现中子能谱的快速获取,准确测量中子辐射场的剂量率,设计了一款一体化多球中子能谱仪。该系统能进行中子能谱的在线测量,实时显示中子剂量率。谱仪在Am-Be参考辐射场进行了验证,测量能谱与标准谱符合较好,转换后剂量率测量值与真值偏差<±7%。     

陆地宇宙射线的中子剂量测量与分析

本文基于多球中子谱仪的设计原理,加工单慢化球多计数器的中子测量探头,搭建多路测量装置,形成了以双球测量方式的少道解谱剂量估算模式,并对陆地宇宙射线的中子辐射场进行测试,得到哈尔滨地区中子所致年剂量约为78 μSv/a。与多球中子谱仪的测量结果相比,中子注量率和中子周围剂量当量率的双球测量结果的相对偏差分别小于3%和12%。     

同位素中子源参考辐射能谱测量及模拟中子谱分析

不同成分中子参考辐射场是对中子防护材料性能测试的基本条件。为获得较理想的测试中子防护材料的中子参考辐射场,构建基于³He正比计数管的多球中子能谱测量系统,对基于²⁴¹Am-Be和²⁵²Cf中子源的中子辐射场慢化情况进行MCNP模拟和能谱实验测量。为准确判断实验室校准参考位置的中子散射情况,基于多球中子能谱测量系统,开展了中子散射成分测量。采用ICRP推荐的注量-剂量转换系数对能谱进行了剂量率转化,与使用长计数器的测量结果进行比较,发现在校准参考位置的剂量率相对偏差≤20%。开展了聚乙烯慢化同位素中子源获得特定能谱的实验研究,进行了慢化谱的模拟计算和实验测量,两者结果符合较好。该工作为后续的中子计量测试和中子防护材料测试提供了可用的中子参考辐射场。     

反应堆堆外中子剂量测量技术试验验证

堆外中子剂量测量技术在反应堆压力容器辐照监督中有广泛的应用。本文介绍了在国内某试验堆上进行的堆外中子剂量测量技术验证试验及其结果。比较了堆外中子剂量测量所用探测片活度的理论计算值、实测值及解谱计算结果,同时分析对比了试验中各辐照位置处中子能谱的理论计算值及解谱结果。结果表明,基于测量值的解谱结果与理论计算结果符合良好。堆外中子剂量测量技术可以有效完成中子能谱测量。     

可逆比热容法测量高中子注量率

目前直接测量高中子注量率一直难于实现，为了解决该问题，本文采用热分析仪器测量受中子辐照后材料可逆比热容的变化来测量高中子注量率。对中国先进研究堆(CARR)辐照孔道的高中子注量率进行了测量，所测量的中子注量率与参考值均在3%左右符合，证明可逆比热容法可直接测量高中子注量率。本文方法是对高中子注量率直接测量的有益尝试。     

西安脉冲堆中子照相束捕集器参数研究

本文建立了用改进的活化法与蒙特卡罗计算相结合测量中子反照率的方法.实验中用激活片直接测量了西安脉冲反应堆中子照相捕集器表面不同位置处的中子总通量,计算中用蒙特卡罗MCNP程序计算了各激活片上正反方向的中子通量比;测量值经过理论计算值纠偏后,确立了测量位置处入射和反射中子的通量,从而确定了捕集器表面的中子反照率分布这一重要参数,为在中子和光子混合场下开展中子照相束捕集器参数测量和实验应用提供了参考.     

Electron emission from carbon induced by the ions C, O, CO and

The secondary electron yield from carbon induced by the ions C⁺, O⁺, CO⁺ and has been measured as a function of ion energy in the range of 2 to 20 keV. It has been observed that electron yield from carbon increases with projectile energy. By comparing electron yields induced by equally fast atomic and molecular projectiles, a molecular effect as a yield reduction has been observed. The measured molecular effect was stronger than the predictions of sweeping-out-electron model.     

X射线及低能γ光子在金属箔透射面的光致电子发射产额

采用改进的密立根光电流测量法,在透射方向测量了＾２４１Ａｍ放射源的Ｘ射线及低能γ光子在透过不同厚度的Ａｌ、Ｆｅ、Ｃｕ、Ｔａ及Ｗ箔时光致电子发射的产额。结果表明：光致电子发射产额在样品厚度范围内随箔厚的增加而减少;在高原子序数材料中将产生更多的光致电子发射。提出了“射程层贡献”模型,以该模型为基础建立的计算方法所得结果与实验值间相对误差平均约为１０％。     

A study of thermal neutron sources

The thermal neutron yield from paraffin spheres 15 and 20 cm in diameter with -Be neutron sources at the center was measured. The neutron yield varied from 0,11 to 0.13 depending on the type of source. Also measured was the neutron spectrum emitted from a sphere 20 cm in diameter heated to 80°C. It was shown that the slow neutron spectrum was satisfactorily described by a Maxwellian distribution with a temperature around 600~ Recommendations are given for the calibration of neutron dosimeters with such sources.Translated from Atomnaya Énergiya, Vol. 15, No. 3, pp. 200–204, September, 1963     

Activation of various materials irradiated by 660 MeV protons

The activity of materials at various times after 4c minute irradiations with 660 MeV protons was measured. The calculated specific activity for a protracted irradiation time varied, depending on the materia, from 15 to 700 g-equivalents Ra/g at 1 hr after irradiation by a proton flux of 10¹⁰ proton/cm²-sec. Good agreement was observed between calculated and experimental data both for the yield of actiVity and for its time rate of decay.Translated from Atomnaya Énergiya, Vol. 15, No. 2, pp. 126–130, August, 1963     

Plasma Focus as a High Intensity Flash X-Ray Source for Biological Radiography

A study on X-ray emission from a low energy (3.3 kJ) plasma focus (PF) device operated with hydrogen is reported. X-ray are detected by using an X-ray detector consisting of three Quantrad Si PIN-diodes with differential filtering and with a pinhole camera. The X-ray yield in different energy windows is measured as a function of hydrogen filling pressure. The maximum yield in 4-geometry is found to be 46.6 J and corresponding wall plug efficiency for X-ray generation is 1.40%. In particular, to demonstrate feasibility of the present PF as a high intensity flash X-ray source for good contrast biological radiography, an X-ray radiogram of a fish, is presented. The fine structure of the specimen can be seen in different parts. The PF, because of its high X-ray yield and good reproducibility is particularly suited for this application.     

Comparison of Measured Soft X-Ray Yield Versus Pressure for NX1 and NX2 Plasma Focus Devices Against Computed Values Using Lee Model Code

The soft X-ray yield versus pressure curves of NX1 and NX2 plasma focus machines have been measured and published for different pressures and electrode configurations. In this work, the numerical experiments are carried out, using Lee model code. The Lee model code is configured for each of these devices NX1 and NX2 by fitting computed total discharge current waveform against a measured total discharge current waveform. The computed soft X-ray yield versus pressure curves are compared with the laboratory measured soft X-ray yield versus pressure data. The comparison shows agreement between computation and measurement of several important features of the yield versus pressure curves.     

Angular dependence of the self-ion-sputtering yield of silicon at 30 keV

The self-ion-sputtering yield of silicon at 30 keV and its angular dependence as measured by nuclear reaction analysis and Rutherford backscattering spectrometry of thin layers are presented. The yield at normal incidence is compared to related data of other groups.     

厚铍靶9Be(d,n)反应中子产额测量

能量在3MeV以下厚靶D-Be反应的中子产额实验数据至关重要,但较为缺乏。本工作在北京大学4.5MV静电加速器上对氘束轰击厚铍靶的中子产额进行测量。对入射氘核能量在0.35~2MeV之间的若干能量点用长中子计数管进行了0°方向中子产额、中子角分布及中子总产额的测量。与已有的测量结果和经验公式进行了比较,并拟合出氘束轰击厚铍靶中子总产额的经验公式。     

Measurements and Simulations of Neutron Emission Versus Deuterium Filling Pressure in Plasma Focus Device PF-24

A series of experiments were carried out using the middle energy (dense) plasma focus device PF-24 with deuterium as a working gas under pressure in a range between 2 and 5 mbar for 17 kV of charging voltage. The relationship between these operating deuterium pressures in reference to the total neutron yield (Y_n) was estimated. The 5-phase Lee code was used to simulate the measured discharge current and neutron yield (Y_n) using a phenomenological beam-target neutron generating mechanism, which was incorporated in the model. Comparison of the Y_n versus pressure using fitted model parameters was made at each point of pressure. The good agreement between measured and computed Y_n values was achieved for discharges with lower neutron emission. The measured Y_n (below 2.6?×?10⁹ n/discharge—the median value) has been reproducible by the model for 73% of simulated discharges, while above the median value its prediction were incorrect. The kinetic plasma parameters which were measured and computed using the Lee code for different pressures are: the time to a current sheath collapse (t_c), the average axial current sheath velocity (v_z) and the so called velocity factor (RF). Good agreement was found in the whole range of deuterium pressures between the computed and measured results for these kinematic quantities. Presented findings in this work suggest that the character of neutron emission is more complex than it would seem from classical interpretation of neutron production based on a beam-target model.     

Calculation of neutron and gamma-ray energy spectra for fusion reactor shield design: Comparison with experiment-II

Measured and calculated neutron and gamma-ray energy spectra resulting from the transport of 14 MeV neutrons through a 0.30-m-thick lithium hydride slab and through a 0.05-m-thick lead slab followed by 0.30 m of lithium hydride are compared. Also reported are comparisons of the measured and calculated neutron energy spectra behind an 0.80-m-thick assembly comprised of stainless steel type 304 and borated polyethylene. The spatial dependence of the gamma-ray energy deposition rate measured using thermoluminescent detectors is compared with calculated data. The calculated data obtained using two-dimensional radiation transport methods and ENDF/B-IV cross-section data are in good agreement for all of the experimental configurations. Calculated integral neutron energy spectra agree with the measured data within 5 to 20% depending on neutron energy for the LiH and Pb plus LiH assemblies. The gamma-ray spectra agree within 20% for these slabs. The measured and calculated neutron energy spectra behind the SS-304-borated polyethylene assembly agree within 5% except at neutron energies below 5 MeV where background radiation influences the measured spectra. The gamma-ray energy deposition rates as a function of depth agree within a factor of two at all detector locations.