密封Cf源的成分测定和中子发射率修正

当密封Cf源寿命超过20年后,其他同位素和子体核素尤其Cf-250和Cm-248的贡献不断增大,使得Cf源中子发射率不能简单按照Cf-252半衰期进行估算。基于Cf源中同位素及其子体核素的衰变和自发裂变规律,提出了一种测定密封Cf源中Cf-252和Cf-250成分的方法,达到快速估算寿命超过20年的Cf源中子发射率的目的。采用长计数器相对测量得到一个使用近30年Cf源在某一时刻的中子发射率,确定了该源初始时刻Cf-252和Cf-250原子核数分别为4.452×1016和7.746×1015,据此给出了Cf源的中子发射率随时间的变化关系。同时在另外两个时刻的推算结果与长计数器测量结果符合得非常好,相对偏差小于0.3%,进一步验证了该方法的可靠性。此外还对Cf-252,Cf-250和Cm-248对中子发射率的贡献与中子源寿命的关系进行了分析,结果表明当Cf源寿命达到30年时,Cf-252对总中子发射率的贡献已经降至67.65%,而Cf-250和Cm-248的贡献已经达到29.32%和2.94%。     

中子学实验近期进展

文章作者采用核活化法和核裂变法实验研究了加速器D-T中子、D-D中子以及~(252)Cf自发裂变中子在纯水泥体上的反射中子,获得了反射中子引起的6种高阈能活化箔的活化反应率以及~(235)U(包镉)和~(238)U裂变反应率.采用反冲质子法测量了4种厚度(4.5,9,18,27cm)聚乙烯板的角度中子谱.获得了聚乙烯铁铍组合壳体内距装置中心0,9.7,12.8和17.3cm 4个位置1MeV以上的中子能谱.采用铝核素标准截面相对测量法,获得了~(175)Lu、~(89)Y核素的(n,2n)反应截面.文章还分析了实验的不确定度.     

中子多重性钚-铀部件质量测量系统及实验进展

为了对核弹头中拆卸下来的和处于库房存储状态的核部件的质量进行无损测量,搭建了一个由32根3 He正比计数管和方型高密度聚乙烯慢化腔体构成的中子多重性探测器,采用8通道电子学处理器件进行中子脉冲信号分析,基于5组252 Cf中子源对中子多重性探测器进行标定,验证了自主开发的标定算法,获取了系统标定参数。分别对6个武器级罐装钚部件,7个罐装铀部件进行中子多重性实验测量,实验分析结果显示:基于点模型修正后的钚部件中子多重性质量测量值与标称值偏差小于1.5%,基于双Am-Li源标定曲线法的铀部件质量测量偏差小于5%。     

248 Cm和252Cf自发裂变瞬发中子谱测量

在飞行时间方法测量 2 0 0keV— 1 2MeV能区内2 48Cm和2 5 2 Cf自发裂变瞬发中子谱 ,以国际原子能机构推荐的2 5 2 Cf自发裂变瞬发中子谱为标准 ,可以免去探测器效率刻度的问题并消除系统误差 ,提高测量精度 .实验用一个微型电离室作为裂变碎片探测器 ,两个芪晶体中子探测器测量中子及一套基于微机的距离分别为 3 2 ,50和 1 0 0cm ,经过对数据的处理和分析给出了 2 0 0keV— 1 2MeV的中子能区内的实验数据 .用Maxwell分布对实验数据进行拟合 ,得到的核温度为 (1 4 0 1± 0 0 0 6)MeV .     

薄壁快脉冲252Cf裂变电离室的研制及性能测试

介绍了用于中子探测器效率刻度的薄壁快脉冲252Cf裂变电离室。 在用飞行时间法测量中子能谱时, 该裂变电离室能够给出252Cf裂变中子发射时刻信号, 输出脉冲上升时间约为5.5 ns, 电离室由厚度为0.15 mm的不锈钢构成。 测试结果表明, 对裂变碎片的探测效率为99.2%, α粒子脉冲幅度和碎片脉冲幅度可清晰分开。A thin wall, fast pulse 252Cf ionization chamber, which was designed for calibrating efficiency of neutron detectors, was described. The ionization chamber can be used as the start detector in time of flight measurements of the 252Cf fission neutron spectrum. The chamber is composed of 0.15 mm thick stainless steel, the rise time of pulse signals is about 5.5 ns. As the test result shows, the detection efficiency of fission fragments is 99.2%, and pulse signals caused by fissions are distinguished clearly from those caused by α decays.     

基于支持向量机的~(252)Cf中子裂变信号时频特征分析及识别

基于裂变中子(252Cf)对裂变链(235U系统)依存关系,在对252Cf中子裂变信号的测量原理及信号特点分析基础上,开展了基于支持向量机的中子裂变信号时频特征分析及识别研究工作。采用小波分解和去噪小波包分解方法,提取不同状态下随机核信号的时频能量特征,借助于统计学习理论的支持向量机(SVM)分类器原理进行训练和分类。研究结果表明:通过直接小波分解或去噪小波包分解,以获取核信号特征的方法是有效的;去噪小波包分解特征提取方式,较之直接小波分解特征提取方式更能反映中子裂变核系统的内部特征和规律;基于SVM核信号样本的分类,训练后的SVM分类器有着大于70%以上的正确率,且较好地克服了训练样本数较少的问题,验证了方法的可行性和有效性。     

基于深度学习的252Cf源驱动核材料浓度识别技术

针对核武器/核材料识别系统中核材料浓度识别的关键技术问题,采用Monte Carlo方法,通过建立252Cf源驱动核材料裂变中子信号样本库,模拟分析了随探测器距离和角度及核材料浓度变化的裂变脉冲中子信号特点,基于深度学习之卷积神经网络,构建了一种252Cf源驱动核材料浓度识别方法,实现了对测试样本浓度的识别,且还与BP神经网络和K最近邻方法进行了对比试验研究。结果表明,卷积神经网络算法进行核材料浓度识别,得到了高达92.05%识别准确率,不仅解决了因探测器距离和角度变化时对核材料浓度识别准确率影响的难题,而且还获得了优于BP神经网络和K最近邻算法对核材料浓度识别的认识,这为252Cf源驱动核材料浓度识别提供了一种新的途径。     

利用252 Cf快裂变室测量BC501A液闪探测器的相对探测效率和响应函数

本文利用²⁵²Cf快裂变室和多参数数据采集系统,逐事例的同时记录了自发裂变中子和瞬发伽马的飞行时间(TOF),脉冲形状甄别(PSD)和反冲能量(RE,裂变中子是通过测量反冲质子;瞬发伽马是通过测量康普顿反冲电子)三维信息.详细介绍了通过离线数据分析完全扣除三维信息中的伽马事例贡献,以获得Φ50.8 mm×50.8 mm的BC501A液闪探测器的相对探测效率和响应函数的方法.在不通过探测器响应函数进行数据转换的条件下,利用中子的能量直接确定了中子的有效测量阈值.得到的中子 关键词： 252Cf快裂变室')" href="#">²⁵²Cf快裂变室 BC501A液闪探测器 相对探测效率 响应函数     

大空腔探测系统中子多重性随机模拟及参数计算

为优化中子多重性探测器设计、指导多重性实验的正确实施,论述了利用蒙特卡罗程序获取中子时间脉冲序列链进行多重性随机模拟的方法。提出了一种新的三均分算法计算中子衰减时间常数,解决了生成时间序列链超大矩阵排序问题。基于大空腔探测系统,利用无死时间的时间序列链经过数据解谱,分析利用252 Cf中子源标定的参数在钚样品多重性测量过程中的匹配问题,考察了探测效率的差异和二阶矩三阶矩的门份额的适用性,并提出了移位寄存器(MSR)处理过程中门宽的优化选取原则。模拟了大量不同质量的钚样品,建立了大空腔探测系统的质量相对标准偏差(RSD)曲线。结果表明:252 Cf源标定的探测效率比Pu样品的效率差3%左右,比值法与公式法计算的门份额完全一致,大空腔探测系统对公斤级的金属钚在1000s时间内的质量测量RSD约为4%。     

屏栅电离室+△E-E望远镜探测器系统

研制了屏栅电离室+△E-E望远镜探测器系统,系统的屏栅电离室用来测定252Cf自发裂变碎片的能量和相对于探测器系统轴线的发射角,与屏栅电离室耦合安装的△E-E望远镜探测器由一个薄的屏栅电离室(气体△E)和一个金硅面垒探测器(E)组成,用来确定互补碎片的电荷.用本系统对252Cf自发裂变碎片电荷分布进行了4个参数的关联测量,结果表明,这个探测器系统的电荷分辨能力Z/△Z好于40:1.     

主动中子多重性铀质量测量模拟研究

中子多重性技术常用于测量和核查核材料,尤其针对具有较厚屏蔽的对象具有不可替代的优势。钚的自发裂变率较高,可以采用被动测量方法,目前已有多款不同的测量装置。然而铀材料的自发裂变率较低只能采用主动测量方法。现有的主动井型符合计数器（AWCC）能够进行主动中子多重性测量铀材料质量,但依然存在探测效率较低,Am-Li中子源产生偶然符合大等缺点。为提高铀材料测量的效率和精度,对主动中子多重性测量方法开展深入研究非常必要。本文参考AWCC模型,利用Geant4软件对探测器和粒子的输运过程进行建模。研究了多重性移位寄存器的不同符合门宽、不同延迟时间对铀测量结果相对偏差的影响规律。计数器的最佳门宽为44 μs,门宽取值范围在计数器衰减时间的1.5倍左右合适;延迟时间大于3倍计数器衰减时间后,相对偏差显著减少。最后讨论了235U富集度变化对主动中子多重性测量结果的影响。为后续主动中子多重性铀质量测量仪器的设计提供了参考。     

基于裂变γ标识技术的瞬发裂变中子谱测量新方法

瞬发裂变中子谱（prompt fission neutron spectrum,PFNS）是用于核实验诊断过程中十分重要的参数数据,传统的测量主锕系核素（U,Pu）PFNS的技术手段是采用裂变室,利用裂变碎片标识裂变中子,通过中子飞行时间技术获得裂变中子谱.目前出现了一种新的用于PFNS测量的技术,其原理是基于如下的物理事实：在一次裂变过程中,释放中子的同时伴随着释放7–8个γ射线光子,而非弹性散射效应产生的γ射线光子只有1–2个.据此,可以通过裂变γ射线的多重性将裂变中子和其他杂散中子甄选出来,达到测量PFNS的目的.本文建立了基于裂变γ标识技术的PFNS测量实验系统.利用该系统对²⁵²Cf中子源的PFNS进行了实验测量,测量结果与传统的裂变碎片标识法及ENDF/B-VⅡ数据库的标准谱进行了比较,对新方法的裂变标识率以及实验不确定度也一并进行了分析.     

Total kinetic energies and mass yield distributions of Cf fission fragments

The variation in the mass yield distribution of the spontaneous fission of ²⁵²Cf as a function of the total kinetic energy (TKE) of the two fragments is investigated. With increasing TKE the peaks of the mass yield distributions become narrower.     

应用于热中子的nTHGEM探测器性能研究

随着脉冲强流中子源的发展,对高性能中子探测器提出了更大的挑战,3He气体资源严重短缺和高计数率中子探测器的迫切需求,已开始制约着中子源应用技术的发展。中国科学院高能物理研究所针对中子的特殊性,专门研发了一种陶瓷基材的nTHGEM（neutron Thick Gaseous Electron Multiplier）探测器用于中子探测。基于nTHGEM的中子探测器具有高计数率、高位置与时间分辨能力、增益大、制作工艺简单,且便于大面积制作的特点,是目前国际上发展替代3He探测技术的重要方向之一。为了详细研究nTHGEM探测器的本身性能,本工作使用55Fe放射源研究了nTHGEM探测器的增益、计数率稳定性、能量分辨率等关键参数与nTHGEM膜间电压、收集场强、漂移场强之间的关系,优化了nTHGEM探测器在不同工作气体中的工作参数,为后续进一步优化nTHGEM探测器设计和工艺奠定了基础。实验结果表明,单层nTHGEM探测器在Ar（90%）+CO₂（10%）混合气体中增益能达到103,探测器计数率稳定性良好。另外,还在中国原子能科学研究院的CARR反应堆（China Advanced Research Reactor）上进行了中子束流实验,通过狭缝测量到探测器位置分辨率为（3.01±0.03）mm（FWHM）,已经接近高气压3He MWPC中子探测器水平。With the development of pulsed intense neutron source, the high-performance neutron detector poses more challenges. The severe shortage of 3He gas resources and the urgent need of neutron detector with high counting rate have begun to restrict the neutron source application technology development. In response to the particularity of neutrons, the Institute of High Energy Physics of CAS developed a nTHGEM(neutron Thick Gaseous Electron Multiplier)of ceramic substrate for neutron detection. The neutron detector based on nTHGEM is one of the most important directions for the development of alternative 3He detection technology in the world at present because of its high counting rate, high position and time resolution, large gain, simple fabrication process and large area production. In order to study the properties of nTHGEM detector in detail, this paper studied the relationship between nTHGEM detector's gain, counting rate stability, energy resolution and other key parameters and nTHGEM film voltage, collection field strength and drift field strength using 55Fe radioactive source, Optimized the working parameters of nTHGEM detector in different working gases, which laid the foundation for further optimization of nTHGEM detector design and process. The experimental results show that the single-layer nTHGEM detector has a gain of 103 in a Ar(90%)+CO₂(10%) mixed gas with good counting rate stability. In addition, a neutron beam experiment was performed on the China Advanced Research Reactor at the China Institute of Atomic Energy, and the position resolution of the detector was (3.01±0.03) mm (FWHM) measured by slits. Its performance is close to the high pressure 3He MWPC neutron detector level.     

Measurement of nanosize etched pits in SiO2 optical fiber conduit using AFM

Fission fragment tracks from ²⁵²Cf have been observed in SiO₂ optical fiber, using an atomic force microscope (AFM), after a very short chemical etching in hydrofluoric acid solution at normal temperature. The nuclear track starting and evolution process is followed by the AFM direct measurements on the material surface and beyond a fine layer of the surface material. The images of the scanned cones were determined observing the two predominant energies from ²⁵²Cf fission fragments and the development of the tracks in the 150 μm diameter optical fiber conduit.     

Monte Carlo calculations and experimental calibrations of Bonner sphere systems with a new cylindrical helium-3 proportional counter

The response functions to mono-energetic neutrons from thermal energy to 20 MeV of eight polyethylene moderating spheres with a cylindrical proportional counter were calculated with the MCNP-4B code for each moderator and confirmed by measurements in wide neutron fields (ISO), as Am–Be and ²⁵²Cf, and with the CANEL and SIGMA IPSN Cadarache (France) facilities, which simulate realistic field and thermal neutron response. With the described spectrometry system, we have carried out neutron measurements at different points from the annular zone inside the containment building of the Vandellòs II Nuclear Power Plant (Tarragona, Spain). The aim of this work is to present the results obtained during the sphere spectrometer development, with reference to the experimental and theoretical aspects and to show that our calculated spectra correspond to points of measurement compared with those obtained using the MORELPA code.     

Use of CR-39 solid state nuclear track detector in neutron personnel monitoring

Neutron sources like ²⁴¹Am–Be, ²³⁹Pu–Be, ²⁵²Cf and 14.6 MeV neutron generator are being used in oil exploration industries as well as in research institutions. While handling these neutron sources, personnel may be exposed to neutrons. Also personnel working in reactors, accelerators may receive dose from neutrons. These exposed individuals need to be monitored regularly for measurement of neutron doses. The individual neutron doses can be estimated by using Kodak NTA films and CR-39 Solid State Nuclear Track Detector with a polyethylene radiator to increase sensitivity in front in holder. Nearly 1450 personnel are being monitored regularly throughout the country on a quarterly basis. In India, the monitoring system adopted for individual neutron dose estimation having energy from 100 keV and above is described in this paper. Background counts of 0.20 mSv could be measured with CR-39 SSNTD foil system and it has been successfully introduced for Fast Neutron Personnel Monitoring for the country.     

中国散裂中子源反角白光中子束流参数的初步测量

中国散裂中子源(CSNS)已于2018年5月建设完工,随后进行了试运行.其中的反角白光中子束线(Back-n)可用于中子核数据测量、中子物理研究和核技术应用等多方面的实验.本文报道对该中子束的品质参数测量实验过程以及最终实验结果.实验主要采用中子飞行时间法,利用~(235)U,~(238)U裂变室和~6Li-Si探测器测量了中子能谱和中子注量率,又利用闪烁体-互补金属氧化物半导体探测系统测量了中子束斑的剖面,得到了该束线的初步实验测量结果.其中白光中子的全能谱测量范围eV—100 MeV,给出了不确定度分析;给出了中子注量率两个实验厅位置的满功率值;给出了白光中子在直径60 mm情况下的全能区束斑.通过与模拟结果的比较探讨了以上结果的合理性,并提出了改进计划.这些实验结果为以后该束线的核数据测量和探测器标定实验奠定了基础.     

Measurement of dose enhancement by neutron capture of boron in Cf interstitial brachytherapy

The effect of boron concentration in water on the gamma, fast and slow neutrons and alpha particles components at the central, forward and backward surfaces inside tumor phantom of 4.2 cm diameter and 4.4cm height, during brachytherapy by neutrons from ²⁵²Cf were investigated. The source was at the centre of a cubic shaped water phantom of 30 cm side. The study was carried for different concentrations of boron from H₃BO₃, Li₂B₄O₇ and H₃¹⁰BO₃. The effect of source to tumor distance on the different components of radiation was also measured. The results indicated that the use of ¹⁰B compounds enhances the damage and is recommended for successful boron neutron capture therapy (BNCT).