固体径迹氡探测器测量国际比对

介绍了浙江省辐射环境监测站(RMTC)、日本化学分析中心(JCAC)和中国疾病预防控制中心辐射防护与核安全医学所(NIRP)三方进行的固体径迹探测器氡测量国际比对.比对结果表明:三方探测器暴露于氡室内不同浓度下的测量值与参考值的相对百分偏差范围在2％～22％,其平均值为8.8％;三方探测器在室内环境中的测量值与三方测量...     

固体径迹探测器测量反应堆功率研究

在零功率反应堆上利用固体径迹探测器直接测量燃料元件内的裂变率，可得到反应堆的功率。同时测量反应堆某位置的热中子通量密度，继而可得到单位功率的热中子通量密度。因此，通过测量该点的任何热中子通量密度即可得到反应堆的运行功率。该方法可以减少与能谱测量有关的修正工作。由于辐照所需的中子通量密度低、时间短，因此与活化法等相比具有明显的优点。     

固体径迹探测器测量快裂变因子

介绍了利用固体径迹探测器测量快裂变因子的原理,方法和实验结果,并将实验结果与理论计算结果进行了比较,两在误差范围内相符合。     

固体径迹探测器测量微型反应堆裂变率

利用固体径迹探测器测量处于微型反应堆不同位置的燃料元件内单位体积的裂变率,得到了堆的裂变率分布和总裂变率,并与其它参数相结合,求得了反应堆功率。同时,测量了对应功率下反应堆内辐照座的热中子通量密度,得到了单位功率的热中子通量密度,从而求得了额定中子通量密度下的运行功率。文章给出的测量方法,避免了其它方法测量功率所引入的近似假设。     

Determination of the Astrophysically Relevant ~6Li(n,γ)~7Li Cross Sections from the ~7Li(~6Li,~7Li)~6Li Elastic-Transfer Reaction

Angular distributions for the ~7(Li)(~6(Li),~7(Li))~6(Li) Li elastic-transfer reaction have been measured with the Q3D magnetic spectrograph at the HI-13 tandem accelerator of Beijing, China. The neutron spectroscopic factors of 7Li are derived by comparing the calculated differential cross sections, which are obtained through the distorted-wave Born approximation (DWBA) calculation, to the experimental data. And these spectroscopic factors are then used to deduce the direct capture cross sections in 6Li(n,γ)7 Li at energies of astrophysical relevance.     

用硝酸纤维素固体径迹探测器记录质子

本文提出一种测定硝酸纤维素径迹探测器纪录质子相对灵敏度的方法,并用该方法确定了富士膜的最佳蚀刻条件。在此蚀刻条件下,测定了富士膜记录质子的灵敏度和效率。     

固体径迹探测器在中子能谱测量中的应用

活化阈探测器法测量中子能谱,主要限于热能区和高能区(0.1MeV以上)的中子谱,其谱型与用不同方法所得的谱型相比差别不大,而中能区(0.55eV～0.1MeV)的谱型相差很远.其原因是缺乏适宜的中能中子的活化探测器。 把固体径迹探测器做为中能中子探测器,它与一组活化探测器结合起来可提供中子全能谱的数据,对现有一般活化探测器不能很好限制中能区域谱型的任意性有所改进。     

固体核径迹探测器测量氡子体平衡因子

本文介绍了用带和不带过滤膜的两个固体核径迹探测器测量氡及其子体平衡因子的原理和方法。用自行设计的这类探测器实验刻度了测量氡及其子体平衡因子的校准系数。所得氡浓度校准系数随相对湿度、含尘量等环境条件变化不大，为１．２０±０．１５（径迹／ｃｍ２）／（ｋＢｑｈｍ－３）；而平衡因子的校准系数则随相对湿度、有无尘源的不同变化较大。此项工作为同时测量累积的平均氡浓度及平衡因子提供了一个初步的、较简便的方法。     

用背对背裂变室测量固体径迹探测器探测裂变碎片的效率

本工作采用自制的背对背裂变室,测量了聚酯(晨光化工厂)和聚碳酸酯(朝阳塑料厂)探测裂变碎片的效率。 1.原理 把裂变室放入热中子场中,测出上下裂变涂层裂变比R。然后,在上裂变室涂层上面压上一片探测器,再放入热中子场中。设下裂变室计数为N_(S(下)),探测器上观察到的径迹数为N_T,则探测器探测裂变碎片的效率ε为     

固体核径迹探测器的最新进展

本文介绍固体核径迹探测器近几年来的主要进展,如发现α反应径迹、合成CR-39-SO_2、气泡损伤探测法,以及在各领域中应用的新进展。     

固体核径迹探测器在中子辐射监测中的应用

介绍固体核径迹探测器近年来在中子辐射监测中的主要进展,其中包括发现CR-39径迹探测器及其主要性能,以及监测中子剂量的方法与应用。     

PETP固体径迹探测器的性能研究

报道了惭烯对苯二酸醌固体核径迹探测器对裂变碎片记录性能的实验研究。在改变温度、蚀刻时间和蚀刻液浓度等条件下测量了裂变碎片迷平均直径的变化。实验结果表明：蚀綮 变化对裂变碎片径迹的影响最大，而浓度和蚀刻的影响不大。同时用低能＾１６Ｏ重离子辐照ＰＥＴＰ探测器，并得到了它的标定曲线。     

固体核径迹探测器在空间育种机理研究中的应用

介绍了将固体核径迹探测器用于空间育种机理研究思路和方法,还简述了探测系统,蚀刻条件和测量参数,讨论了粒子鉴别方法,最后对大田培育的性状变异与物理探测结果之间的相关性进行了分析。     

238U and 232Th concentrations measured in different medical drugs by using solid-state nuclear track detectors and resulting radiation doses to the skin of patients

Urban populations in Morocco receive free medical drugs as prescribed by doctors in district health centres.To explore the exposure pathway of ~(238)U and~(232)Th and their decay products on the skin of patients,these radionuclides were measured in various medical drugs by using solid-state nuclear track detectors(SSNTDs).The measured concentrations range of ~(238)U and ~(232)Th in the medical drug samples of interest vary from(4.3±0.3) to(11.1±0.7) mBq 1~(-1) and(0.49±0.03) to(1.3±0.1)mBq 1~(-1),respectively.A new dosimetric model,based on the concept of specific alpha-dose and alpha-particle residual energy,was developed for evaluating radiation doses to skin following the application of different medical drugs by patients.The maximum total equivalent effective dose to skin due to the ~(238)U and ~(232)Th series from cutaneous application of different medical drugs by patients was found to be 2.8 mSv year~(-1) cm~(-2).     

Determination of Li-6/Li-7 Isotopic Ratio by Means of Thermogravimetric Analysis for Lithium Sulphate Monohydrate

Plutonium concentrations and burnup at Pu spots were calculated in U-Pu mixed oxide (MOX) fuel pellets for light water reactors with the neutron transport and burnup calculation code VIMBURN. The calculation models were suggested for Pu spots and U matrices in a heterogeneous MOX fuel pellet. The calculated Pu concentrations and burnup at Pu spots were compared with the PIEs data in a MOX pellet (38.8 MWd/kgHM). The calculated Pu concentrations agreed by 5–18% with the measured ones, and the calculated burnup did by less than 10% with the estimated one with the measured Nd concentrations. Commercial PWR types of MOX fuels were also analyzed with the calculation code and the models. Burnup at Pu spot increased as the distance was greater from the radial center of a MOX fuel pellet. Burnup at Pu spots in the peripheral region became 3–5 times higher than pellet average burnup of 40 MWd/kgHM. The diameters (20–100 μm) of Pu spots were not found a significant factor for burnup at Pu spots. In the outer half volume region (outer than r/r _o=0.7) of a MOX fuel pellet, burnup at Pu spots exceeded 70MWd/kgHM (the threshold burnup of microstructure change in UO₂ fuel pellet) at pellet average burnup of 1430 MWd/kgHM.