中子气泡探测器性能改进及初步检验

对自制中子气泡探测器进行了改进。对改进后探测器的个人中子剂量响应以及重现性、批内一致性在国防科学技术工业委员会放射性计量一级站的中子仪表刻度实验室进行了检验。结果显示,探测器的重现性、剂量响应和批内一致性等主要特性有了大幅提高。     

自制个人中子气泡探测器特性的批内一致性

采用252Cf中子源和2×1.7MV串列加速器产生的14.8MeV单能中子源,对自制的12批中子气泡探测器的批内一致性进行测试。结果表明,在室温条件下,同批次制作的气泡探测器性能符合ISO标准。     

固体气泡损伤探测器中子探测效率的刻度

在２＊１．７ＭＶ串列加速器上用＾７Ｌｉ（ｐ,ｎ）＾７Ｂｅ、Ｔ（ｐ,ｎ）＾３Ｈｅ、Ｄ（ｄ,ｎ）＾３Ｈｅ和Ｔ（ｄ,ｎ）＾４Ｈｅ核反应产生的２０ｋｅＶ－１９ＭｅＶ单能快中子对中国原子能科学研究院研制的固体气泡损伤探测器进行了刻度。这种探测器可用于中子能谱和中子剂量测量。     

三种中子探测器探测效率对比

利用了实验室的标准γ源和Am-Be中子源,搭建了简单的中子探测器系统结构,研究了涂硼稻草管(BCS)和⁶LiF/ZnS(Ag)闪烁体中子探测器的γ甄别率与相对于³He管的中子探测效率。对比发现BCS的γ甄别率低至10^-8,而⁶LiF/ZnS(Ag)闪烁体的γ甄别率预计在10^-6。BCS和⁶LiF/ZnS(Ag)闪烁体相对于3He管的单位面积下中子探测效率分别为106.55%和218.12%。满足了替代³He的基本要求。     

NTD硅探测器

采用国产NTD硅单晶,研制了性能较好的NTD硅探测器。用它精确测定14MeV中子能量和作为γ射线计数器均取得了较满意的结果。其性能指标为:反向偏压1kV,漏电流≤5μA,26℃;对~(241)Am α源,FwHM为31-50KeV,26℃;对~(137)Cs 625 keV的内转换电子,FwHM为6.85LeV,-2℃。     

外照射个人剂量监测探测器的研究进展

介绍了我国目前最广泛应用的LiF:Mg,Cu,P的研究新进展和优越性能及不足;介绍了新材料LiF:Mg,Cu,Si热释光片状探测器的最新研究进展;介绍了最新发展起来的α-Al2O3:C的光释光的优缺点及进展。     

基于3层硅探测器的主动式中子个人剂量计研制

研制了一种具有能量分辨能力的中子个人剂量计。该个人剂量计由3层硅探测器组成,硅探测器周围装有⁶LiF、聚乙烯和含硼聚乙烯作为转化体、慢化体和吸收体。个人剂量计有直读和解谱两种工作模式。直读模式将中子能区划分为低能、中能和快中子3个能区,可实时测量。解谱模式可获得快中子能区的中子能量分布。利用GEANT4程序模拟了7 MeV γ射线的能量沉积谱,设置适当的甄别域以降低γ射线的影响。采用GEANT4程序模拟了个人剂量计对不同能量入射中子的个人剂量当量率响应。在加速器单能中子参考辐射场中完成了单能中子剂量响应的实验校准,对模拟计算的响应函数进行了实验修正,并得出了不同能区的平均中子个人剂量当量率响应。     

Study on Batch Homogeneity of Personal Neuron Bubble Detectors

本工作通过对^45Sc（n，γ）和（n，2n）反应截面实验测量数据的收集、筛选、分析和修正，并与理论模型分析相结合，对原先的评价数据进行改进，得到最终的推荐结果。与此同时，重新评价了（n，p）、（n，α）、（n，nα）、（n，T）和（n，^3He）等反应道的截面数据。     

微结构半导体中子探测器研究进展

微结构半导体中子探测器(MSND)除了具有体积小、时间响应快、工作偏压低以及易于与读出电子学系统集成等优点外,还解决了二维平面半导体中子探测器存在的探测效率极低的问题(5%),其在军用和民用领域都具有良好的发展前景。介绍了微结构半导体中子探测器的中子探测原理,简述了其发展概况,综述了近年来的研究进展,展望了微结构半导体中子探测器的研究方向和应用前景。     

Study on Reproducibility of Home-Made Personal Bubble Neuron Detectors

Reproducibility is an important parameter of bubble detectors used for personal neutron dose monitoring. This study presents a preliminary analysis on reproducibility of home-made bubble detectors using ISO standards as guidelines. Moreover the software ＂origin＂ was used in an attempt to find possible reasons causing some detectors failed to pass this test.     

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。     

Neutron Dosimetry with Boron-Doped CR-39 Plastic

As a highly sensitive, simple and non-radioactive neutron dosimeter, CR-39 plastic plates doped with a boron compound: ortho-carborane were prepared. After thermal neutron irradiation, the plates were etched in an aqueous solution of 30%KOH, at 60°C for 2 to 16 h. The etch-pits generated by ¹⁰B(n, α)⁷Li reactions were then counted using an optical microscope or an automatic track counting system. The density of the etch-pits on an irradiated plate increases with the etching time. When the etching time is kept constant, the etch-pit density is proportional to the irradiated thermal neutron fluence. The proportional constant is termed “sensitivity”, which is 4.2 x 10^?4 for a plate containing ortho-carborane at a concentration of 0.5% by weight and for etching time of 16 h. By considering background counts, a thermal neutron dose of 0.025 mSv can be measured with this plate. The plates are insensitive to visible-, UV-, X-, β- and γ-rays and are easy to handle because the detector and converter are incorporated. There is no possibility of underestimating the dose equivalent due to fading. Furthermore, the isotopes of boron are not radioactive and thus are radio- logically safe.     

中子图像探测器的量子探测效率

为研究由中子-可见光图像转换屏、光学系统以及CCD相机组成的中子图像探测器的成像性能,根据探测效率、量子增益和调制传递函数等性能评价参数,分析了中子探测效率与闪烁体厚度的关系以及薄板型和阵列型闪烁体与CCD相机之间采用不同耦合方式下的量子增益,并给出了透镜耦合条件下的调制传递函数及相应的量子探测效率,最后全面分析了中子图像探测器的等效噪声量子数。     

Neutron and Gamma Sensitivities of Dynamic Detectors

The neutron and gamma sensitivities of nine detectors were studied in experiments performed at the Sandia Pulsed Reactor (SPR). Of the detectors tested, six are predominantly gamma detectors at the SPR and three produce a significant fraction of their total current due to the neutron flux during a normal SPR burst. None of the detectors studied were found to be predominantly sensitive to the neutron flux during a normal SPR burst. Tests performed at pure gamma sources on a P-Intrinsic-N (PIN) diode detector are also described. The neutron induced current in the silicon detectors is treated theoretically.     

空腔理论在固体剂量计中的应用

在Burlin空腔理论基础上提出了1个经修改后可适用于兆伏级X(γ)能量固体剂量计的新空腔理论。它通过Monte-Carlo方法分别计算固体剂量计空腔内的初级光子粒子注量和散射光子粒子注量及它们相应产生的次级电子粒子注量，并按空腔尺寸所对应的电子射程，把高能和低能光子分开，计算初级光子和散射光子沉积在固体剂量计灵敏体积中的能量，即吸收剂量。为验证该空腔理论，用半导体固体剂量计在6MV医用电子直线加速器上进行了水模体输出因子测量，并模拟相同测量条件用新空腔理论对水模体输出因子进行了理论计算，其测量结果与计算结果在0.5%内符合。     

Characteristics of Fabricated Neutron Detectors Based on a SiC Semiconductor

Wide-band-gap semiconductors such as SiC, AlN, and GaN are promising materials for harsh environment applications due to their high-temperature operation capability. Two types of PIN-type semiconductor neutron detectors based on SiC were designed and fabricated for nuclear power plant (NPP) applications such an in-core reactor neutron flux monitoring and safeguarding nuclear materials. One is for fast neutron detection and the other, which was evaporated with ⁶LiF, is for thermal neutron detection. In this study, preliminary tests, such as the determination of I-V and alpha responses, were performed. Reaction probabilities with respect to neutron energies were also calculated by using an MCNPX code for comparison with the experimental results. Responses of the neutrons were measured at the Ex-core Neutron irradiation Facility (ENF) of the High-flux Advanced Neutron Application Reactor (HANARO) research reactor at the Korea Atomic Energy Research Institute (KAERI). Pulse height spectra and count rates were measured with respect to the neutron fluxes from 1:6 × 10⁶ n/cm²·s to 1:9 × 10⁷ n/cm²·s. Also, a 0.99 root-mean-square value of linearity against the fluxes to the count rates was obtained with the fabricated neutron detectors. For a thermal neutron detector, a 3.3% detection efficiency was obtained.