进口锆英砂放射性γ能谱分析

利用γ能谱分析技术对2个产地共17个进口锆英砂样品中的放射性核素226Ra、232Th和40K进行了定量分析,并提出了一种新的样品自吸收修正方法。结果:产地1样品中226Ra的比活度均值为2399.75Bq/kg,232Th的比活度均值为422.72Bq/kg;产地2样品中226Ra的比活度均值为1852.91Bq/kg,232Th的比活度均值为455.45Bq/kg;2个产地样品中40K的比活度均很低。研究表明,锆英砂样品中放射性主要来源是226Ra、232Th。两产地样品中232Th的放射性比活度相差较小,而226Ra的放射性比活度差别明显。同一产地样品中放射性核素比活度也存在较大差异。样品自吸收对分析结果的影响可达10%—30%,须进行自吸收修正。     

Monte Carlo simulation of indoor external exposure due to gamma-emitting radionuclides in building materials

The use of building materials containing naturally occurring radionuclides such as^40K,^238U,^232Th and their progeny, could lead to external exposures to the residents of such buildings. In this paper, a set of models are constructed to calculate the specific effective dose rates（the effective dose rate per Bq/kg of ^40K, the ^238U series,and the ^232Th series） imposed on residents by building materials with the MCNPX code. The effect of chemical composition, position concerned in the room and thickness as well as density of material is analyzed. In order to facilitate more precise assessment of indoor external dose due to gamma-emitting radionuclides in building materials,three regressive expressions are proposed and validated by measured data to calculate specific effective rates for40 K,the238U series and the232 Th series, respectively.     

Measurement of intrinsic radioactive backgrounds from the ~(137)Cs and U/Th chains in CsI(Tl) crystals

The inorganic Cs I(Tl) crystal scintillator is a candidate anti-compton detector for the China Dark matter Experiment. Studying the intrinsic radiopurity of the Cs I(Tl) crystal is an issue of major importance. The timing,energy and spatial correlations, as well as the capability of pulse shape discrimination provide powerful methods for the measurement of intrinsic radiopurities. The experimental design, detector performance and event-selection algorithms are described. A total of 359×3 kg-days data from three prototypes of Cs I(Tl) crystals were taken at China Jinping Underground Laboratory(CJPL), which offers a good shielding environment. The contamination levels of internal isotopes from137 Cs,232Th and238 U series, as well as the upper bounds of235 U series are reported.Identification of the whole α peaks from U/Th decay chains and derivation of those corresponding quenching factors are achieved.     

Monte Carlo simulation of indoor external exposure due to gamma-emitting radionuclides in building materials

The use of building materials containing naturally occurring radionuclides,such as ⁴⁰K, ²³⁸U, ²³²Th and their progeny, could lead to external exposures to the residents of such buildings. In this paper, a set of models are constructed to calculate the specific effective dose rates (the effective dose rate per Bq/kg of ⁴⁰K, the ²³⁸U series, and the ²³²Th series) imposed on residents by building materials with the MCNPX code. The effect of chemical composition, position concerned in the room and thickness as well as density of material is analyzed. In order to facilitate more precise assessment of indoor external dose due to gamma-emitting radionuclides in building materials, three regressive expressions are proposed and validated by measured data to calculate specific effective rates for ⁴⁰K, the ²³⁸U series and the ²³²Th series, respectively.     

光谱和能谱法测定磷矿渣中放射性元素的含量和比活度

本文用红外光谱和X－射线衍射法研究了磷矿渣的基本成分,其主要相组成为玻璃体。用偶氮胂Ⅲ光度法测定了矿渣中铀和钍的含量,并用γ谱测定了放射性核素^226Ra,^232Th和^40K的比活度,为了解磷矿渣对环境的污染程度及其综合利用提供理论依据。     

ICP-MS法测定人体器官中Cs,Th和U的分布

采用ICP-MS对10种人体器官组织样品中的痕量Cs, Th和U进行了研究, 选择了最佳仪器工作参数, 用Rh为内标元素补偿基体效应和灵敏度漂移, 检出限为Th 5.7×10-3, U 1.04×10-2, Cs 1.78×10-2 ng·mL-1. 随同样品分析了NIST SRM 8414牛肌肉和NIST SRM 1486骨粗粉标准参考物质, 测得值与标准参考值吻合. 用HNO3和HClO4混合酸消解样品, 不须分离富集, 直接对人尸体的肺、肝、骨胳、甲状腺、小肠、胃、肌肉、肾、脾和心脏中痕量Cs, Th和U进行测定. 结果表明 ICP-MS方法可以准确、精密地测定人体器官中的微量Cs, Th和U; 这3个元素在人体各个器官的分布各异, 例如Th和U主要分布在肺和肾, 而Cs则在全身相对均匀分布; 来自不同省市的肺部Cs, Th和U含量之间具有显著性差异, 且同一地区人肺样品中的Cs, Th和U浓度呈现同升共降的趋势, 说明Cs, Th和U在人体器官的积蓄和各地的环境、饮食相关.     

Measurement of intrinsic radioactive backgrounds from the 137Cs and U/Th chains in CsI(Tl) crystals

The inorganic CsI(Tl) crystal scintillator is a candidate anti-compton detector for the China Dark matter Experiment. Studying the intrinsic radiopurity of the CsI(Tl) crystal is an issue of major importance. The timing, energy and spatial correlations, as well as the capability of pulse shape discrimination provide powerful methods for the measurement of intrinsic radiopurities. The experimental design, detector performance and event-selection algorithms are described. A total of 359×3 kg-days data from three prototypes of CsI(Tl) crystals were taken at China Jinping Underground Laboratory (CJPL), which offers a good shielding environment. The contamination levels of internal isotopes from ¹³⁷Cs, ²³²Th and ²³⁸U series, as well as the upper bounds of ²³⁵U series are reported. Identification of the whole α peaks from U/Th decay chains and derivation of those corresponding quenching factors are achieved.     

232Th 中子诱发裂变产额数据比对评价

232Th 中子诱发裂变产额在Th/U 燃料循环的核能开发中具有重要的意义,在现有国际评价产额数据库基础上,结合最新的实验数据,对产物核的质量分布和反应堆计算所需的重点产物核进行了比对。这些产物核包括95Mo,99Tc,101Ru,103Rh,109Ag,133Cs,147Sm,149Sm,150Sm,151Sm,152Sm,143Nd,145Nd 和153Eu 等,对有分歧的133Cs,152Sm 和153Eu 累积产额数据进行了评价调整。最后推荐给出了n+232Th 裂变的产额数据库,作为CENDL 库的组成部分。The yields of n+232Th fission are important in study of the Th/U fuel cycle. Based upon the evaluated nuclear data libraries and recent experimental data,comparison and evaluation for yield mass distribution and cumulativeyield were performed for those products are needed and important in reactor calculations,including 95Mo,99Tc,101Ru,103Rh,109Ag,133Cs,147Sm,149Sm,150Sm,151Sm,152Sm,143Nd,145Nd adn 153Eu etc. Adjustments were made for 133Cs, 152Sm and 153En which have discrepancies among the libraries. Database for n+233Th fission yield is recommended as a part of CENDL update.     

北航沙河校区土壤中40 K、238 U、232 Th相对含量的实验测量

环境中天然伽马射线主要来源于40K以及钍系、铀系和锕系.通过探测伽马射线来识别放射性核素并得到它们的相对含量,是核科学与核技术中的一个重要方法.利用高分辨的高纯锗探测器,北航以及国内部分高校已开设了鉴别环境中放射性核素的实验.在此基础上,本文进一步利用特征γ射线与递次衰变规律,对北航沙河校区土壤中的40 K、238 U...     

垒下熔合裂变中观察到的异常

测量了¹⁶O+²³²Th、²³⁸U和¹⁹F+²³²Th近垒和垒下熔合裂变截面以及碎片角分布.包含靶核静态形变的耦合道理论解释了垒下熔合截面增强,预言了复合核系统自旋分布展宽.而实验上观察到的碎片角分布各向异性明显与裂变统计理论的预言不一致.     

核裂变碎片角分布与鞍点核形状

用天然白云母作为裂变碎片探测器,测量了78兆电子伏¹²C离子轰击¹⁶⁹Tm、¹⁷⁵Lu、¹⁸¹Ta、¹⁹⁷Au、²⁰⁹Bi、²³²Th、²³⁸U等7种同位素以及能量为96.6 92.288.1 79.0 75.6兆电子伏的¹⁴N离子轰击天然Pb的裂变反应碎片角分布.用哈尔彭（Halpern）和斯图金斯基（Strutinski）裂变碎片角分布理论符合,从碎片角分布各向异性计算可裂变核在鞍点的有效转动惯量.实验上推出来的鞍点核形状同液滴模型的理论予示作了比较.     

~(13)C(α, n)~(16)O background in a liquid scintillator based neutrino experiment

α from natural radioactivity may interact with a nucleus and emit a neutron. The reaction introduces the background to the liquid scintillator(LS) based neutrino experiments. In the LS detector, α comes from 238 U,232Th,and 210 Po decay chains. For Gadolinium-doped LS(Gd-LS) detector, α also comes from 227 Ac. The nucleus 13 C is a natural component of Carbon which is rich in the LS. The background rate and spectrum should be subtracted carefully from the neutrino candidates. This paper describes the calculation of neutron yield and spectrum with uncertainty estimated. The results are relevant for many existing neutrino experiments and future LS or Gd-LS based experiments.     

Assessment of Primordial Radionuclides in Pakistani Red Bricks and Associated Radiation Doses

Specific activity of primordial radionuclides and associated radiation hazards due to 40K, 226Ra, and 232Th have been measured in backed red brick samples, collected from five highly populated areas of the North West Frontier Province of Pakistan. For the detection, analysis and data acquisition, a high purity germanium detector was used. Associated external doses were calculated using a Monte Carlo neutron photon transport code. A theoretical model to determine the gamma dose rate at 1 m height from the floor, made of bricks, was employed for the calculation of mass attenuation coefficient and self-absorption in the floor for the gamma energies of these radionuclides and their progeny. Monte Carlo simulation shows that in this study the floor, having more than an effective thickness of 15 cm, contributes very little to the external gamma dose rate. The values of the external dose rate and annual effective dose are found to be much lower than the world average as well as from other countries of the world.     

Digital logarithmic airborne gamma ray spectrometer

A new digital logarithmic airborne gamma ray spectrometer is designed in this study. The spectrometer adopts a high-speed and high-accuracy logarithmic amplifier (LOG114) to amplify the pulse signal logarithmically and to improve the utilization of the ADC dynamic range because the low-energy pulse signal has a larger gain than the high-energy pulse signal. After energy calibration, the spectrometer can clearly distinguish photopeaks at 239, 352, 583 and 609 keV in the low-energy spectral sections. The photopeak energy resolution of ¹³⁷Cs improves to 6.75% from the original 7.8%. Furthermore, the energy resolution of three photopeaks, namely, K, U, and Th, is maintained, and the overall stability of the energy spectrum is increased through potassium peak spectrum stabilization. Thus, it is possible to effectively measure energy from 20 keV to 10 MeV.     

稀土尾矿砂放射性活度的测量与计算分析

准确测量并计算稀土尾矿砂的放射性活度浓度及其变化规律对制定相应的豁免标准和日后的处理处置具有重要的意义。根据选取的特征 射线,分析对比平衡与非平衡状态下铀系、钍系、锕系三个天然衰变系的总活度浓度,结合衰变链的一般动力学方程,计算总放射性活度与每个核素的放射性活度,并研究钍系各核素在平衡被不同程度破坏的情况下随时间的变化规律。结果显示,按照非平衡情况下计算得出的总α 和总β 放射性活度浓度比平衡情况下的更接近实际测量结果,此外,钍系核素在平衡被破坏后的放射性活度随时间变化情况与母体和228Ra 的初始放射性活度浓度有关,若228Ra 小于232Th,则总放射性活度在60 a再次平衡后达到最大值,为10 倍的母体活度;若228Ra 大于232Th,则总放射性活度在3.82 a 出现最大值,为4.57 倍母体活度与5.25 倍第一子体228Ra 的初始活度浓度之和。因此,可知稀土尾矿砂放射性活度已经遭到破坏,其总活度浓度应该采用非平衡情况下的几个特征核素的活度浓度共同计算得到,并且需计算分析其随时间变化出现的最大值,以此来确定是否超过相关法规标准。It is of great significance to measure and calculate rare earth tailing radioactivity for the development of appropriate standards and exemption disposal. The total activity concentration of the three natural decay series (uranium series, thorium series, actinium series) was analyzed under the equilibrium and disequilibrium state according to the selected characteristic  γ-rays. At the same time, we calculated the total activity concentration and the radioactivity for each radionuclide based on the general kinetic equations of decay chain and studied the trend of each radionuclide of thorium-series under different degrees of disequilibrium with time. The results demonstrated that the total radioactivity of and calculated in disequilibrium state was more closed to the actual measurement results compared to that in equilibrium state. In addition, the activity changes with time of thorium series in disequilibrium state are related to the initial activity concentration of the mother nuclide and 228Ra. If the activity concentration of 228Ra is less than that of 232Th, the total activity peak will be 10 times to maternal activity and appear after 60 a when the thorium series become balance again. If the activity concentration of 228Ra is greater than that of 232Th, the maximum total activity will appear in 3.82 a, and will be the sum of 4.57 times of the initial activity concentration of the mother nuclide and 5.25 times of the initial activity concentration of the first daughter 228Ra. Therefore, the rare earth tailings have been in disequilibrium state, and its total activity concentration should be determined based on the activity concentration of several  feature radionuclides. In addition, the maximum value of the activity concentration is profitable to judge whether the activity concentration is fit with relevant regulations and standards.     

环带钾长石、榍石和锆石的显微结构与微区组成特征分析

南秦岭沙河湾石英二长岩中的钾长石、榍石和锆石具有明显的成分环带。利用电子探针(EPMA)波谱仪(WDS)、扫描电子显微镜(SEM)及其附带的能谱仪(EDS)和激光剥蚀电感耦合等离子体质谱(LA-ICP-MS)对造岩矿物环带钾长石、榍石和锆石的显微结构与微区组成进行表征。结果表明：钾长石中K+被Na+,Ca2+,Ba2+,Fe2+和Ce3+不同程度替代。榍石中Ca2+被V3+,Ce3+和Ba2+等替代,Ti4+被Fe2+和Al3+等替代。锆石含Fe,Th,U,Nb,Ta,Y,Hf,Yb和Pb等稀土和微量元素。钾长石中元素浓度由高到低为Si,Al,K,Ca,Na,Mg和Ba,其中K和Na互补,较亮处Ba含量高,越靠近边缘,Si升高、K升高与Na降低趋势越明显。榍石中元素浓度由高到低为Ca,Si,Ti,Ba,V,Ce,Al和Fe,较亮处Fe含量较高。锆石中元素浓度由高到低为Zr,Si,Nd,Ce,Hf,U,Pb和Th,Hf与Zr呈明显的互补关系,核部Zr含量较边部高,核部Hf、U和Th含量较边部低。     

微波消解-电感耦合等离子体质谱法同时测定烟草中27种元素

在烟草中的有机和生物活性成分被鉴定出来之后,分析和鉴别其中的无机元素就变得非常重要。采用电感耦合等离子体质谱法同时测定了烟叶中Be,Na,Mg,K,Ti,V,Cr,Mn,Fe,Co,Ni,Cu,Zn,As,Se,Sr,Mo,Ag,Cd,Sn,Cs,Ba,Hg,Tl,Pb,Th和U共27种元素。样品的前处理采用硝酸和过氧化氢混合溶液。通过在线加入内标液的方法来校正由于基体效应和信号漂移对测量所造成的影响,内标选用锗、铟和铋3种元素。方法的回收率为93.64%～108.9%,检出限为0.356 3 ng·L-1～1.725 μg·L-1,相对标准偏差1.28%～9.18%。实验结果表明该方法能满足痕量分析的要求。     

平均场加区分质子和中子的邻近轨道对力模型及对超铀区核的统一描述

利用严格可解的平均场加区分质子和中子的邻近轨道相互作用对力模型,对超铀区部分大形变核进行了统一的描述.计算了^227—233Th,^232—239U,^236—243Pu同位素和同中异质素²²⁸Ra-²²⁹Ac-²³⁰Th-²³¹Pa-²³²U,²³²Th-²³³Pa-²³⁴U-²³⁵Np-²³⁶Pu,²³⁶U-²³⁷Np-²³⁸Puv-²³⁹Am的结合能,对激发能和奇偶能差并与相应核的实验值进行了比较     

双硫腙四氯化碳萃取微乳液进样火焰原子吸收光谱法同时测定天然水中的铅和锌

双硫腙四氯化碳萃取分离富集天然水样中的铅、锌 ,微乳液进样火焰原子吸收光谱法同时测定铅、锌的含量。对 Pb、Zn的混合溶液进行 7次平行测定 ,RSD分别为 2 .9%、1 .7%,对水样测定的平均回收率分别为 97.5 %、1 0 3%。     

无放射源伽马能谱测量实验设计

为了在无放射源的前提下开设γ能谱测量实验,本文使用氯化钾样品中的40K代替常规放射源,研究了所需的实验样品含量、实验装置和实验内容,并分析了本实验的辐射危害情况.研究表明:使用氯化钾样品不仅可以满足常规γ能谱测量的实验要求,还比仅使用137Cs放射源丰富了实验内容,且经计算和测量本实验的辐射剂量达不到放射源的下限标准,可以保证学生在安全的前提下完成实验内容.本研究设计的实验方法不受放射源使用手续及环保部门的制约,有利于消除学生的放射性恐惧心理,减少放射源的管理成本及非核类院校的γ能谱测量实验课程的开设.