用组合叠层CR-39固体径迹探测器测量加速器厚铍靶9Be(d,n)反应中子能谱

采用组合叠层CR-39固体径迹探测器实验方法测量了加速器D（d,n）反应产生的5MeV与2MeV准单能中子能谱。进而测量了入射氘离子能量为3MeV时加速器厚铍靶9Be（d,n）反应的中子能谱,与已有的飞行时间法的测量结果基本相符。在此基础上,用该法又测量了入射氘离子能量为1．5MeV时加速器厚铍靶9Be（d,n）反应的中子能谱,结果符合较低能量氘离子与厚铍靶发生9Be（d,n）的核反应的物理过程。     

厚靶T(d,n)4He反应加速器中子源的中子产额、能谱和角分布

本文给出一种氚钛厚靶氘氚反应加速器中子源的中子产额、能谱和角分布的计算方法,并开发了相应的计算模拟程序。用自行开发的计算程序计算了入射氘束流能量低于1.0MeV时加速器中子源的中子产额、能谱和角分布,给出了氚钛厚靶的一些典型计算结果,并对结果的可靠性进行分析。     

厚靶T(d,n)4He反应加速器中子源的中子产额、能谱和角分布

本文给出一种氚钛厚靶氘氚反应加速器中子源的中子产额、能谱和角分布的计算方法,并开发了相应的计算模拟程序.用自行开发的计算程序计算了入射氘束流能量低于1.0 MeV时加速器中子源的中子产额、能谱和角分布,给出了氚钛厚靶的一些典型计算结果,并对结果的可靠性进行分析.     

国产Am-Be中子源能量低于1.5MeV中子所占份额的实验测定

本工作提出了测定Am Be中子源发射的能量低于1.5MeV中子所占份额的1种实用实验方法。用4.438MeVγ射线伴随的飞行时间法测量了中子源的局部中子谱（n₁群中子）。通过已准确测量的中子源发射4.438MeVγ射线与中子强度的比值(R=R_γ/S_n)和n₁群中子谱与测量的能量为1.5MeV以上中子总谱在3.2MeV能量处归一后的面积比值,求得国产Am-Be中子源能量低于1.5MeV中子的所占份额为(19.1±1.9)%。     

光电倍增管中子直照响应实验研究

采用脉冲束中子飞行时间法和脉冲电荷计数法相结合的多参数测量方法,在中国原子能科学研究院HI-13串列加速器上,利用9Be(d,n)10B反应白光中子源,实验研究了光电倍增管对0.75～15MeV之间的出射中子直照灵敏度。根据光电倍增管的工作原理,采用MCNP程序模拟计算了光电倍增管的中子直照灵敏度。分析表明,计算结果与实验结果基本一致。     

离子源及厚靶参数对氘氚反应中子源中子产额的影响

用厚靶氘氚(D-T)反应中子产额的计算方法模拟计算了入射氘离子能量为120 keV时D-T中子源的中子产额。研究了氘离子源产生的束流中单原子氘离子(D+)及双原子氘离子(D2+)比例对中子产额的影响。结果表明,提高D+比例,同时降低D2+比例将有效提高中子产额。另外还研究了不同靶膜材料及组分引起的中子产额变化。表明中子产额与靶膜中氚的含量成正比,与靶膜元素的原子质量成反比。同时分析讨论了离子源品质及靶参数对中子源整体性能的影响,得出离子源束流品质的提高对中子源整体的设计至关重要。最后,模拟计算了靶膜表面有氧化层情况下中子产额的变化,并与实验结果作了对比。在此基础上提出了一种新的靶设计方案,并对其物理可行性进行了研究。     

基于固体靶的D-T和D-D中子源特性模拟计算

基于氚(氘)钛固体靶,利用TARGET程序结合实际的氚(氘)靶和靶室建模,对D-T中子和D-D中子的能量和微分截面角分布、氘离子能量损失率和平均能量、中子平均能量和能散、反应率在氚(氘)钛靶中的深度分布、中子注量率谱和中子产额进行了计算,获得了D-T和D-D中子的相关特性参数。计算结果可为在其他蒙特卡罗模型中精确描述各项异性中子源提供数据,对中子能量单色性和中子产额等指标的选择提供了参考数据。     

^18O离子轰击厚靶的中子剂量学参数

用阈探测器活化法测量了每个核子动能（简称单核能）为５０ＭｅＶ＾１８Ｏ离子轰击厚靶（Ｂｅ、Ｃｕ、Ａｕ）时出射中子的能量分布、注量率分布和中子角分布，得到了＾１８Ｏ离子的中子产额、前向中子发射率和中子剂量当量率分布的数据。并与国外报道的单核能在２０ＭｅＶ以下的低能重离子轰击厚靶研究中得到的中子剂量学参数进行了比较和分析。     

可用一台ADS验证装置的150 MeV固态金属散裂中子靶的性质研究

对可以用于中国“加速器驱动洁净核能系统”的入射质子能量为150MeV,束流为3 mA的固态金属靶进行了研究。采用锥型几何结构作为靶的结构,材料选择钨,靶厚度为3 mm,对“靶-束窗”一体化结构进行了研究。研究了泄露中子产额和中子产额,泄露中子的能谱分布和空间分布,散裂碎片的分布以及能量沉积和辐射损伤。     

用屏栅电离室测量~6Li(n,t)~4He反应微分截面

用屏栅电离室对 3.6 7MeV与 4 .4 2MeV中子6Li(n ,t) 4He反应微分截面进行了测量。利用氘气体靶通过D(d ,n) 3 He反应产生中子 ,用BF3 和液闪探测器 (NE2 13)进行相对中子通量监测 ,绝对中子通量用2 3 8U(n ,f)与H(n ,p)反应来刻度。测量结果表明 ,氚的质心系微分截面在中子能量为 3.6 7MeV时很接近 90°对称 ,而到 4 .4 2MeV时则明显前倾     

Measurements of induced activity in concrete by secondary particles at forward direction produced by intermediate energy heavy ions on an Fe target

Spallation and neutron capture reaction rate distributions were measured using activation detectors inside a 90-cm thick ordinary concrete pile exposed to a field of secondary particles escaping a thick (stopping length) iron target bombarded with various intermediate energy ions, 230 MeV/u He, 400 MeV/u C, and 800 MeV/u Si. Activation detectors of aluminum, bismuth, gold, and gold covered with cadmium were inserted at various depths in the concrete pile. In addition, the distributions of activation reaction rate were simulated by FLUKA and PHITS Monte-Carlo codes. Generally, comparison of measured and calculated reaction rates show agreement within a factor of two. The experimental data will be useful for benchmarking Monte-Carlo radiation transport simulation code capabilities in estimating radioactivity induced in accelerator radiation shielding.     

Target optimization for a 10-MeV E-beam neutron converter

Accelerator-based target design and optimization is an approach for neutron generation. The target plays an important role for a neutron source on an electron accelerator. For optimizing a neutron source using 10 MeV electron beams of Rhodotron-TT200, Pb, Ta, or W alloys with Be were calculated as photo-neutron converter. The neutron yield, flux and energy were simulated using the MCNPX code. The results indicate that a 10 MeV electron beam is capable of producing high-intensity neutron flux of 1013n·cm–2·s–1 with average energy of 0.8 MeV.     

~(115)In中子非弹性散射截面的实验测量及蒙特卡罗修正

~(115)In是一种重要的活化材料,准确测量它的中子非弹性散射截面数据对中子注量监测具有重要意义。在四川大学原子核科学技术研究所2.5 MV静电质子加速器上,利用核反应D(d,n)~3He产生的单能中子,以~(197)Au作为标准,采用活化法测量了2.95 Me V、3.94 Me V、5.24 Me V能点的~(115)In中子非弹性散射截面。用Monte Carlo程序MCNPX(Monte Carlo N-Particle eXtended)对靶头材料、冷却水层和样品的包层材料等引起的多次散射效应及注量率衰减效应等进行了修正计算,得到最终结果与Loevestam的计算值符合较好,并且实验中可通过减小靶管、靶底衬、水层及样品的包层材料等厚度来减小多次散射效应和自屏蔽效应的影响。     

Recent progress in nuclear data measurement for ADS at IMP

Recent progress in nuclear data measurement for ADS at Institute of Modern Physics is reviewed briefly.Based on the cooler storage ring of the Heavy Ion Research Facility in Lanzhou, nuclear data terminal was established.The nuclear data measurement facility for the ADS spallation target has been constructed, which provides a very important platform for the experimental measurements of spallation reactions. A number of experiments have been conducted in the nuclear data terminal. A Neutron Time-of-Flight(NTOF)spectrometer was developed for the study of neutron production from spallation reactions related to the ADS project.The experiments of 400 MeV/u ~(16)O bombarded on a tungsten target were presented using a NTOF spectrometer.Neutron yields for 250 MeV protons incident on a thick grain-made tungsten target and a thick solid lead target have been measured using the water-bath neutron activation method. Spallation residual productions were studied by bombarding W and Pb targets with a 250 MeV proton beam using the neutron activation method. Benchmarking of evaluated nuclear data libraries was performed for D-T neutrons on ADS relevant materials by using the benchmark experimental facility at the China Institute of Atomic Energy.     

Measurement of Gamma-Ray Production Cross Sections of Iron for Incident Neutron Energies between 6 and 33 MeV

Measurement of differential γ-ray production cross sections, i.e. (n, x γ) cross sections, of Fe was made for neutron energies from 6 to 33 MeV. Neutrons used in the experiment were white neutrons produced with (p, n) reactions by 35 MeV protons using a thick Be target. The neutron energy was analyzed by the time-of-flight method and bunched into 3 MeV wide energy bins, for each of which the spectrum of secondary γ-rays produced in an Fe sample was measured by a BGO scintillator at an angle of 144° to the neutron beam direction.

The obtained (n, xγ) cross sections agreed well with other data and the evaluated data file of ENDF/B-IV at neutron energies below 15 MeV where data were existing. The JENDL-3 file overestimated the γ-ray spectra at γ-ray energies of 3 to 7 MeV. The present work newly provided the data in the neutron energy range above 20 MeV. The GNASH calculation made by Young reproduced the measured data fairly well even at these higher energies.     

重离子加速器实验靶区的中子剂量当量率

用阈探测器中子活化法测量了５０ＭｅＶ／ｕ＾１８Ｏ离子轰击Ｂｅ、Ｃｕ、Ａｕ厚靶出射中子的注量率分布,并利用中子注量率对剂量当量率的转移因子,得到了重离子实验靶区的中子剂量当量率分布。     

1.4MeV-5MeV中子诱发~(238)U裂变产额测量

~(238)U裂变产额测量工作在核数据测量中有着重要意义,本工作利用2.5MeV质子静电加速器产生的1.4MeV-5MeV单能中子诱发238U裂变,通过对裂变产物放射性的测量对裂变产物核素~(135)I、~(133)I、~(105)Ru和~(91)Sr的产额进行了测定。照射过程中中子通量用活化法确定。分析了影响实验测量的多个因素,包括用MCNPX程序对中子在靶头及样品中的多次散射和自屏蔽效应进行了修正,对γ射线在样品中的自吸收进行修正等。得到产额数据典型误差为3.5%,最后把测量结果与已有的裂变产额数据进行比对。     

Induced Activity of a Tungsten Target in a 10 MeV Electron Accelerator

Experiments are performed to determine the isotopic composition of the induced activity of a tungsten target for a 10 MeV electron beam. The measurement results are used to calculate the dose rate from the induced activity of the target for an accelerator with 100 kW beam power. It is established that ¹⁸⁷W radiation makes a substantial contribution to the dose rate. The neutron yield from the target and the flux density of neutrons scattered in the accelerator room are estimated.     

AB-BNCT中子靶物理设计分析

质子加速器适用于为硼中子俘获治疗提供中子源,其中子源强及能谱较反应堆中子源更具可调性。中子靶物理计算分析是加速器中子源设计的基础,为其提供粒子能量、流强等参数需求分析,并为靶体结构尺寸设计、中子慢化和屏蔽分析等提供前端参数。本文利用MCNPX蒙特卡罗程序,通过对质子打靶的中子产额和能谱、靶体能量沉积、打靶后靶材放射性活度和中子出射空间角分布等进行研究,提出能量2.5 MeV质子轰击100～200 μm锂靶的设计,并用模拟计算数据论证其合理性。该设计中子源在1 mA流强质子轰击下,源强可达9.74×10¹¹ s^-1;拟设计15 mA、2.5 MeV质子束产生的中子源,在治疗过程中靶材放射性活度累积最大值约为1.44×10¹³ Bq。     

Evaluation of D(d,n)3 He reaction neutron source models for BNCT irradiation system design

A mathematical method was developed to calculate the yield,energy spectrum and angular distribution of neutrons from D(d,n)~3He(D-D)reaction in a thick deuterium-titanium target for incident deuterons in energies lower than 1.0MeV.The data of energy spectrum and angular distribution were applied to set up the neutron source model for the beam-shaping-assembly(BSA)design of Boron-Neutron-Capture-Therapy(BNCT)using MCNP-4C code. Three cases of D-D neutron source corresponding to incident deuteron energy of 1000,400 and 150 key were inves- tigated.The neutron beam characteristics were compared with the model of a 2.45 MeV mono-energetic and isotropic neutron source using an example BSA designed for BNCT irradiation.The results show significant differences in the neutron beam characteristics,particularly the fast neutron component and fast neutron dose in air,between the non-isotropic neutron source model and the 2.5 MeV mono-euergetic and isotropic neutron source model.