Fast neutron flux measurement and spectroscopy using silicon semiconductor detectors

A method is developed for measuring fast neutron fluxes and spectra using small silicon semiconductor detectors in the presence of relatively high gamma radiation levels. A general formula is derived for calculating the averaged cross section and the effective energy. Good agreement is found between the calculation and experimental data. The sensitivity of the method is much higher than that of any other threshold neutron detector with comparable size.     

几种闪烁探测器的中子能量响应函数测量

采用直流刻度方法．实验研究了ST401、ST1422或ST1423塑料闪烁体加光电倍增管组成的探测器的裂变中子灵敏度,获得了中子灵敏度随中子能量的变化关系。实验结果与计算进行了比较．在不确定度范围内符合很好。     

一种提高液体闪烁绝对测量探测效率的方法

介绍了如何提高3H、14C样品的探测效率,进行了计量技术的研究.使用4πβ(LS)活度国家基准刻度3H、14C溶液的放射性活度.     

Eu活化过渡法测量绝对热中子注量率

在相同条件下,以不同时间辐照Ａｕ箔和Ｅｕ箔,用γ谱仪测量＾１９８Ａｕ的４１１ｋｅＶγ射面积和＾１５２Ｅｕ的４１１ｋｅＶγ峰面积,再通过４πβ－γ符合装置测得金箔的绝对中子注量率,根据两者的峰面积之比和测得的Ａｕ箔绝对中子注量率,求得＾１５３Ｅｕ的４１１ｋｅＶγ峰面积对应的中子注量率。     

Development of self-powered neutron detectors for neutron flux monitoring in HCLL and HCPB ITER-TBM

Self powered neutron detectors (SPND) have a number of interesting properties (e.g. small dimensions, capability to operate in harsh environments, absence of external bias), so they are attractive neutron monitors for TBM in ITER. However, commercially available SPNDs are optimized for operation in a thermal nuclear reactor where the neutron spectrum is much softer than that expected in a TBM. This fact can limit the use of SPND in a TBM since the effective cross sections for the production of beta emitters are much lower in a fast neutron spectrum.This work represents the first attempt to study SPNDs as neutron flux monitors for TBM. Three state-of-the-art SPND available on the market were bought and tested using fast neutrons at TAPIRO fast neutron source of ENEA Casaccia and with 14 MeV neutrons at the Frascati neutron generator (FNG).The results clearly indicate that in fast neutron spectra, the response of SPNDs is much lower than in thermal neutron flux. Activation calculations were performed using the FISPACT code to find out possible material candidates for SPND suitable for operation in TBM neutron spectra.     

The thermal-neutron capture cross-section of 55Mn

The ratio of the thermal-neutron capture cross-sections of H and Mn can be measured with high accuracy in the course of measurement of neutron-source emission rates in Mn bath systems in which the chemical concentration of the MnSo₄ solution is varied. Three recent measurements of this ratio are used in conjunction with the capture cross-sections for H and Mn taken from the latest Brookhaven compilation to produce a value for the Mn cross-section with significantly reduced uncertainty. The recommended value is 13.41 ± 0.04 b. A simultaneous evaluation of all standard thermal-neutron capture cross-sections would enable some of the improvement in the uncertainty for Mn to influence the values and uncertainties of other cross-sections.     

绝对测量220Rn的小闪烁室的研制

详细介绍了一种用于绝对测量^220Rn的结构特殊的ZnS(Ag)小闪烁室。并进行了测氧比对实验,得到它对^222Rn／^220Rn及其子体的探测效率可达到96％以上。通过串接此闪烁室测量管道气体流量,与标准流量计的测量结果比较,误差在5％以内。     

利用金属钆测量热中子通量的实验研究

研究了一种测量热中子通量的新方法,利用金属钆与热中子反应产生的次级γ射线来确定热中子通量。使用两个NaI探测器进行符合测量,设计了对伽玛射线和散射中子的良好屏蔽体。经过对本底和钆样品的多次测量,对钆与中子反应产生的伽玛能谱进行了分析,计算出了中子与钆反应产生的计数率(样品净计数率),其最大值达到2.74 Hz,从而证实了这种方法的可行性。     

加速器中子源的中子注量测量方法

在用静电加速器中子源标定探测器的中子灵敏度实验中,采用“BF3长计数管 定标器”系统过渡,用^197Au中子活化分析方法达到了对中子注量在线、绝对监测的目的。这种方法给出与加速器束流不同角度、不同距离处的中子注量。介绍了这种中子注量测量方法。