基于6LiF/ZnS(Ag)和闪烁光纤的宽能谱中子探测技术研究

为了解决传统中子探测器在狭窄空间、强电磁干扰、远距离传输等复杂环境下探测中子时存在的不足,本研究将6LiF/ZnS(Ag)混合材料和闪烁光纤相结合,设计了一种可用于宽能谱中子测量的新型闪烁体光纤中子探测器。基于蒙特卡罗粒子输运计算程序FLUKA对该新型光纤中子探测器的中子探测性能进行了模拟研究,完成了闪烁体光纤探头的优化设计。结果表明,当入射中子的能量在0.01~10 eV和0.5~10 MeV范围时,该新型中子探测器具有较高的中子探测效率,可用于热中子-快中子宽能谱范围中子的探测;通过对比脉冲幅度的差异,该新型中子探测器能够实现n-γ信号的甄别。      

圆柱氧化钍装置上的中子及伽马穿透能谱实验测量

利用D-T中子对氧化钍圆柱装置进行了辐照。样品直径为30 cm、厚度为15 cm。在不同的布局状态下,采用芪晶体闪烁体基于反冲质子法对1 MeV~15 MeV中子能谱进行了实验测量;基于反冲电子法对中子辐照下和辐照后的0.5 MeV以上伽马能谱进行了测量。对能谱中的分布规律、与布局状态的关系进行了比对分析。     

B4C/Al对慢中子衰减性能研究

本文用Burrus模型和蒙特卡罗方法,模拟中子透过B4C/Al板的衰减规律。在Burrus模型中,选用0.025 3eV中子为中子源,B4C/Al板厚度为0.15cm,0.20cm,0.25cm,0.30cm,0.35cm,其中B4C的质量百分含量为20%,30%,40%。结果表明,在B4C/Al复合材料中,B4C含量越高,颗粒越小,材料的中子吸收效果越好,中子透射率越小。入射到B4C/Al板的中子,在B4C/Al板的穿透率与入射角方向有关,垂直与B4C/Al相互作用时,中子透射出的概率最大,随着入射角弧度增大,中子在B4C/Al板的透射率逐渐变小。蒙特卡罗方法使用MCNP程序对B4C/Al与中子的相互作用进行模拟,结果表明,B4C/Al板对能量为0.025 3eV的中子比1.0eV的中子有更大的吸收效果。     

强流加速器D-Be中子源中子慢化引出研究

为优化成像中子束注量率和能谱,在考虑中子源能谱、角分布、面源结构及靶系统条件下,利用MCNP程序模拟源中子的慢化和输运过程,记录不同模型时慢化体内热中子注量率分布和成像中子束成分。结果表明,聚乙烯更适合用作小型热中子源慢化反射材料;D+束轰击靶面的束斑大小影响热中子在慢化体内的分布,束斑半径在1cm内变化对中子慢化影响较小;增加热中子引出孔道与D+束轴线的夹角能有效提高引出热中子束的纯度。     

油砂地层井眼水源距对中子-伽玛能谱影响的模拟

介绍了中子-伽玛能谱测井中研究中子-伽玛射线随空间、能量、时间分布的蒙特卡罗(Monte Carlo)模拟软件包.在裸眼井、井眼里无下井仪器、油饱和砂岩地层、井眼注淡水等条件下,用该软件包计算了井轴和井壁的不同源距(和垂距)地层中子-伽玛射线随能量、时间的分布,以及井轴和井壁在各种源距下的中子-伽玛射线能谱,亦即研究了源距变化对中子-伽玛射线随能量、时间分布以及井轴与井壁中子-伽玛射线能谱的影响.     

钒球14 MeV中子的泄漏能谱测量

建立了厚度为 1 0 5cm的金属钒球基准实验装置。钒的纯度为 99 9%。用NE 2 1 3谱仪测量了d T中子的 0 75～ 1 5MeV泄漏中子能谱 ,能量大于 0 75MeV的中子的穿透率为 0 84± 0 0 3 ,中子能谱实验误差为 5 %～ 7%。用MCNP/ 4AMonte Carlo程序和FENDL 2库核数据进行了模拟计算 ,并与实验结果进行了比较     

用不同程序模拟计算ADS散裂靶结果的比对(英文)

利用不同的程序对ADS散裂靶进行了模拟计算。用SNSP,SHIELD,DCM\CEM(Dubna Cascade Model\Cascade EvaporationMode)和LAHET等程序计算了长60 cm,直径20 cm的圆柱形铅靶,分别在800,1000,1500 and 2000 MeV的质子轰击下所产生的泄漏中子产额和能谱分布。模拟结果与实验数据进行了比较,对泄漏中子产额而言,SNSP模拟的结果与实验符合较好,SHIELD,DCM\CEM和LAHET计算的泄漏中子能谱分布比较一致。     

中子能谱在反应堆屏蔽计算中的应用分析研究

在反应堆的屏蔽设计中多采用蒙特卡罗中子-光子耦合输运程序(MCNP)计算反应堆压力容器和堆内构件的中子注量率,用以评估中子对结构材料的辐照损伤。MCNP在计算这类固定源问题时,源强的能量分布多采用MCNP自带的Maxwell裂变中子能谱或Watt裂变中子能谱,它们是典型能量的入射中子对应的向量裂变能谱。然而真正的裂变中子能谱是与入射中子能量相关的矩阵裂变中子能谱。为此,不同的中子能谱对反应堆屏蔽设计计算结果的影响被分析。结果表明:在反应堆屏蔽设计中应考虑不同能量的入射中子对裂变中子能谱的影响,即应该采用矩阵裂变中子能谱进行反应堆屏蔽设计计算。     

长白山区土壤中~(90)Sr、~(239+240)Pu纵向分布研究

研究了~(90)Sr、~(239+240)Pu在同一点位土壤中的纵向分布情况和迁移特性。在长白山未受人类活动影响的点位分层采集不同深度的土壤样品,用放射化学的方法测量样品中~(90)Sr、~(239+240)Pu的活度浓度。研究发现:在同一点位,表层土壤中~(90)Sr、~(239+240)Pu活度浓度比深层土壤高,且这种分布趋势非常明显;随着深度增加,~(239+240)Pu活度浓度迅速减少,~(90)Sr活度浓度则是逐步减小。研究表明:采样点土壤中~(239+240)Pu向下的迁移不明显,主要分布在0~10 cm的表层土壤中,而~(90)Sr则有一定程度的迁移,但在0~10 cm的表层土壤中含量最高。     

D-T中子照射下贫化铀球、钒球介质内中子能谱和伴生γ能谱测量

为获得介质内中子能谱及伴生γ能谱的实验数据，在中心D-T中子照射下，用18mm×20mm的茋闪烁体探测器，测量了与D+束成45°角的水平方向距球心7、10、13、16、19、22cm位置处贫化铀球介质内的中子能谱和伴生γ能谱，以及钒球内与D+束成0°角、距离球心1.8、4.8和8.3cm处的中子能谱和伴生γ能谱。用MCNP/4B程序和ENDF/B-VI库数据对实验模型进行模拟计算，并与实验结果进行了比较。     

Radiation Effects on GaAs Charge Coupled Devices with High Resistivity Gate Structures

The results of a study on the effects of 1 MeV electrons and 1 MeV neutrons on the operation of high speed GaAs Charge Coupled Devices (CCDs) are presented. Radiation-induced trapping levels are characterized using a linear array CCD structure and the periodic pulse technique. 1 MeV electron irradiation introduced traps at 0.1 eV and 0.39 eV with bulk trap introduction rates of 1 cm-1 and 0.33 cm-1, respectively. The devices were irradiated to a maximum fluence of 9×1014 electrons/cm2. 1 MeV neutron irradiation introduced an electron trap level at 0.64 eV with a bulk trap introduction rate of 0.5 cm-1. Catastrophic device failure occurred at neutron fluences of 6×1013 neutrons/cm2. Device charge transfer efficiency was characterized pre- and post-irradiation over the temperature range of 80°K to 300°K.     

Variation of environmental neutron flux with altitude and depthof both water and soil

Applying the extreme low-level y-ray spectroscopic analysis the environmental neutron flux is measured using different moderator construction and environment through the reaction ^197Au (n, γ) ^198Au- The contribution of thermal and resonance neutrons is separated using the cadmium difference technique, while fast neutrons are measured by the paraffin moderator. The results of altitude dependence of the neutron flux are discussed. The thermal neutron flux near the surface of sea water is less than its value at 100 cm over ground near sea water, while the value over the surfaces of fresh water is higher than that near the surface of sea water. Also the thermal neutron flux at 5 cm soil depth increases, then decreases to its original value at 10 cm depth and still constant until 25 cm, then decreases rapidly to reach 27% of its original value at 60 cm depth. The soil compositions, corresponding neutron temperatures and effective absorption cross sections of earth are the most effective factors on the equilibrium region of thermal neutrons in the ground.     

A Method of Isotopic Ratio Determination of Uranium by Ge(Li) Detector

The effect of the presence of a reentrant hole for extracting the neutron beam from within experimental systems of two different geometries is analyzed theoretically with use made of multi-group 2- dimensional discrete S_n method without resorting to bold assumptions for neutron transport nor drastic simplification of geometry. One of the two experimental systems is a rectangular light water prism 12 cm high of 40 × 40 cm² cross section, poisoned with Cd and/or In, and provided with a 1, 2 or 3 cm diameter reentrant hole. The other system is a 1″ thick natural uranium plate sandwiched between two layers of pure light water, each 4.6 cm thick, which also is provided with a 1cm diameter reentrant hole.

The following is concluded by comparing the angular neutron flux with and without the reentrant holes. With the first experimental system, perturbations of the order 10～25% is caused, which is particularly strong below about 0.3 eV, except when the hole diameter is 1cm. The perturbation effect increases as the reentrant hole becomes larger in diameter and shallower in depth. In the case of the second experimental system, the effect results in about 2% increase of the neutron flux at the bottom of the reentrant hole when the bottom is located in the natural uranium plate. On the other hand, if the bottom is in the light water region, the neutron flux is reduced by about 2～4% at the peak of the thermal neutron spectra.     

基于150 MeV电子束的光中子特性模拟分析

高能中子源是研究高能太空宇宙射线中子对人体和电子仪器辐射损伤的必备装置,基于高能电子加速器的光中子源是目前能够提供较高能量白光中子的方式之一。本工作以清华大学先进加速器实验室的激光电子加速器束流参数为基础,借助Geant4对产生的光中子的能量特性、产额特性、角分布特性、时间特性进行了分析。模拟结果表明,Φ2 cm×2 cm的圆柱体Ta靶时,150 MeV电子束流可产生最高能量约为110 MeV、中子产额约为1.2×10~5n/10~7e-、出射时间在0~100 ns之间呈负指数分布的几乎各向同性的光中子。根据拟合的中子能量-出射时间离散指数函数,估算得到对产生的1~100MeV中子,在飞行距离为5m时中子飞行时间的时间分辨率好于2.23%。本工作为该加速器的光中子产生和实验测量工作提供了参考依据。     

基于TMSR-PNS装置0.008〜0.1 eV能区Th的全截面测量

Th是Th-U燃料循环的起始核素,其核数据精度关系到Th-U转换性能。基于TMSR-PNS中子源采用透射法对高纯ThO2样品进行测量,得到ThO2的全截面实验数据。利用ENDF/B-Ⅶ.1库中氧的评价数据,扣除氧的全截面,得到Th的全截面。测量结果显示,Th的全截面在0.02~0.1 eV能量范围测量数据的不确定度为3.25%~4.51%,与ENDF/B-Ⅶ.1库评价数据差异在实验误差范围内。中子能量小于0.02 eV时Th的全截面实验数据出现了布拉格散射结构,其与ENDF/B-Ⅶ.1库UO2的U热中子散射截面类似。     

BNCT人头体模内剂量分布计算

用修正的Synder人头体模几何模型和ICRU-46中的材料数据，用MCNP-4B程序对0．0253ev、1kev、2keV、10keV、100keV、1MeV单能中子束，0．2、0．5、1、2、5、10MeV单能光子束，以及与当前硼中子俘获治疗(BNCT)临床中使用的超热中子相似的超热中子束，计算了在人头体模中的剂量分布，计算结果与有关文献报道的结果一致，初步校验了我们正在编制的BNCT治疗计划软件。     

Noise analysis of a zero power critical line reactor using Langevin's technique

Noise analysis of a critical, infinite-length, zero-power line reactor is given using the Langevin technique. A one-speed model is used and delayed neutrons are ignored. Stochastic analysis is carried out starting from the Boltzman equation with the assumption that neutrons move only in both directions in the line reactor. The power spectrum of neutron fluctuations is obtained and compared with that computed from diffusion approximation. Exact expressions for auto and cross-power spectrums of non-fission neutron detectors' outputs are also obtained.     

The neutron tissue dose

This paper is devoted to the determination of dosimetric characteristics of intermediate-energy neutrons. A calculation of the interaction of neutrons with paraffin for the normal incidence of an extended beam of neutrons in the energy interval from 100 ev to 1 Mev, which has been performed by means of an electronic computer, is given here. The computation results are used for calculating the components of the neutron tissue dose resulting from the moderation process in the tissue. The dose resulting from the neutron capture is calculated on the basis of the authors' data on the distribution of slow neutrons in paraffin and on neutron reflection from the surface of a hydrogenous medium. The depth distributions of neutron dose components for thermal neutrons and neutrons with energies of 100 ev, 1, 30, 240, 500 kev, and 1 Mev were obtained. The depth distributions of the biological dose for neutrons of the same energy and the biological dose values pertaining to the unit neutron flux were obtained.     

Investigation of the Neutron Angular Distribution and Neutron Yield on the APF Plasma Focus Device

This paper presents an experimental study of neutron yield as well as neutron angular distribution on the APF plasma focus device. The system operates with pure deuterium gas in varying the filling pressure and working voltages of 11.5 and 13.5 kV. The maximum average of neutron yield is (2.88 ± 0.29 × 10⁸) neutrons per shot at the pressure of 7 torr. The neutron angular distribution is measured with housing an array of seven silver activation Geiger-Muller counters at the angles of 0°, ±30°, ±60°, and ±90° in a distance of 90 cm from the anode tip. The results of neutron angular distribution suggest that the neutron production mechanism may be predominantly beam target model.     

液闪探测器中子光响应函数刻度研究

BC501A液体闪烁体在临近空间高能中子测量中具有重要的应用价值,其光响应和能量分辨率对测量结果影响较大。对中子与BC501A液体闪烁体作用产生的反冲质子的光响应函数以及液闪的能量分辨函数进行了研究。利用5SDH-2串列加速器通过核反应获得单能脉冲中子源,实验获得单能中子的脉冲幅度谱,应用GEANT4等MC软件对实验进行模拟计算得到光响应谱,并与脉冲幅度谱进行拟合得到各能点中子的光输出以及其对应的能量分辨率,应用最小二乘法对中子光响应函数以及能量分辨函数进行了计算,并将计算结果与推荐光响应函数进行了对比分析。结果显示:模拟计算反冲质子能谱与单能中子脉冲幅度谱在末端边沿处拟合效果较好,中子光响应函数与其他文献中的研究结果基本一致。