离子交换法提取大量钍中微量铀

采用浓盐酸溶解ThO_2和U_3O_8、以Dowex1×8阴离子交换树脂和Dowex50×8阳离子交换树脂作离子交换剂,研究了从大量钍及微量裂变产物(FPs)中提取微量铀的方法。考察了裂变产物元素Cs、Sr、Y、Zr、Nb、Ru、Rh、La、Ce、Eu的去污效果。结果表明,用离子交换法可以实现从百克每升Th及FPs中分离出微量U。最优工艺条件是料液调至8mol/L HCl介质,大量Th和微量的FPs在8mol/L HCl-0.2mol/L NH4F洗涤条件下直接通过阴离子交换柱,而U吸附于树脂上,再用0.05mol/L HNO_3淋洗U。低HNO_3淋洗U后,直接过阳离子柱吸附微量Th,再用2mol/L HNO_3淋洗得到纯U。结果表明,U收率大于98%,产品中Th及FPs的含量均小于0.05μg/L。     

Preparation of Beryllium Targets by Vacuum Evaporation

The apparatus is shown in Fig.1, which is mounted within a conventional metal bell jar 45 cm in diameter and 70 cm high. The boat source could be seen through the windows of the appratus and the bell jar.There was no straight-line exit from the apparatus to the interor of the bell jar for Be vapor originating at the boat.Tantalum boat, 13 mm wide, 28 mm long, and 0.1 mm thick, was used as evaporation source. The distance from the boat to the substrate was 15 cm. Microscope glass slide coated with betaine as substrate.The Be foils produced by resistance heating were removed from the glass by dissolving the     

Research of On-line Analytical Method of Trace Oxygen and Water in Argon

Metal sodium has an active chemical quality. When it is used as a coolant in a fast neutron reactor, it must be protected by a cover gas argon for safety operation of the reactor. But oxygen and water in argon can produce chemical reaction with sodium. Then sodium hydroxide, sodium oxide and hydrogen can be produced. This will be harmful to the safety operation of reactor. The purpose of controlling a level of impurity in the cover gas is for controlling a level of impurity in sodium. The research is to find an on-line determining method and a sampling system to monitor     

金属铍中杂质元素的ICP-AES分析方法研究

研究用HCl溶解金属铍,在HNO3介质中用磷酸二丁酯(DBPA)-苯萃取,将铍与待测杂质元素分离,用ICP-AES法测定Co、Mn、Mg、Cr、Si、Cu、Al、Ni 8种杂质元素的含量.取样量为40 mg时,上述杂质元素的测定范围在5.0×10-4%～0.1%之间,方法回收率为95%～104%,相对标准偏差优于10%(n=6).     

Beryllium as reflector of MNSR

The article deals with beryllium reflector effects on criticality of a miniature neutron source reactor, and the study of these effects for various cross-section evaluations. D-shape plates of beryllium are added on top of the reactor core to enhance reactivity of the system during operation. Fuel cycle analysis was carried out using SARC code. It was observed that reactivity effects of a particular thickness of beryllium remain nearly same during the whole life of the core. Up to 11% differences were observed between measured and calculated results for various libraries. The nearest match with the measured results was found for JENDL-3.2 library having maximum deviation of 5%.     

Analysis of Pulsed Neutron Experiment in Beryllium by the Method of Inelastic Scattering Expansion

Pulsed neutron experiments in beryllium have been analyzed by the method of inelastic scattering expansion. Considering the full range of energy, the present method is applied to the calculation of the time dependent spectra within a system as well as at its surface. For obtaining the decay curve of the neutron counting rate, the neutrons are classified according to the number of specified inelastic scatterings that scatter the neutrons over the Bragg cutoff energy. The pseudo mode is, as a principal result, shown to correspond to an eigen solution of the thermal bounded equation. The buckling dependence of the eigenvalue and the eigen spectrum of the thermal bounded equation are studied, and useful approximate expressions are derived. The calculated results are compared with the experiments by Fullwood et al. and other authors.     

X射线法测试铍材表层应力沿深度的分布

X射线应力分析是一种基于X射线衍射原理的无损应力检测方法,应用于铍材时,由于铍的密度低以及对X射线质量吸收系数小,X射线对铍材有较大穿透深度,因此,X射线法可以测试铍材表层一定深度内的应力.由于铍材表层应力分布往往不均匀,常规X射线应力分析法测试铍材应力存在误差,无法得到沿深度的应力分布.本工作根据常规X射线应力分析时不同侧倾角ψ下X射线穿透深度的不同,建立了一种适于铍材表层应力沿深度分布的测试方法,并用悬臂梁加载实验验证了该方法的可行性.     

Beryllium erosion induced by transient heat loads and subsequent reactions in a deuterium plasma

Pulsed laser irradiation (～0.1–4 MJ/m² at 1–10 ms) to a beryllium (Be) target has been performed under steady-state deuterium (D) plasma exposure in the linear divertor plasma simulator PISCES-B to investigate the response of Be to transient heat loads such as edge localized modes. Emission intensities from Be atoms and beryllium deuteride (BeD) molecules are observed in front of the Be target by using two fast framing cameras simultaneously; those exhibit similar time evolution to each other, but spatial profiles are different. While the Be I light emission peaks just in front of the target, the BeD emission peaks away from the target. This indicates that Be atoms are directly ejected from the surface, and BeD molecules are volumetrically formed in the plasma. It is also found that the time evolution of light emission can be qualitatively well reproduced by the evaporation flux of Be atoms, estimated from the calculated surface temperature. The Be surface is thought to be eroded as atoms due mainly to evaporation during laser irradiation.     

MRPC探测快中子研究

介绍了多气隙电阻板室(MRPC)的结构和原理,用蒙特卡罗方法计算了MRPC对快中子的灵敏度,并进行了脉冲中子实验。实验表明,MRPC有望用于飞行时间法测量快中子能谱。     

痕量镎和钚的ICP-MS分析方法

经TOA萃取色层柱分离环境样品,2次上柱,将Np和Pu同时洗脱,239Pu的化学回收率为 (92.7±3.1)%,237Np为(96.8±2.7)%,实现了ICP-MS同时测定痕量Np和Pu的含量.应用稀释剂242Pu,通过同位素稀释ICP-MS法测量痕量239Pu和240Pu的含量,用IAEA标样对方法进行验证,Pu 的测定值与标样的推荐值吻合较好(标样中无Np的标准值),证明了ICP-MS同时测定痕量Np和Pu的可行性.     

用质子激发X射线分析方法进行人发微量元素的分析研究

一、序言 质子激发X射线分析方法是瑞典人约翰逊在1970年首先提出来的。由于它具有灵敏度高、取样少、无损伤、快速、适用范围广等特点,使它在十余年中在生物医学、环境科学、地质、冶金、考古学和法学等领域得到了广泛的应用。我们应用质子激发X射线分析方法分析了人发中的微量元素。     

氙光源液体荧光法分析尿中微量铀

利用HNO3+HClO4+H2SO4的氧化体系,对尿样前处理方法作了改进,可更彻底地去除尿中的有机物。方法改进后处理的样品适用于以氙为光源的MUA型微量铀分析仪测量,相对标准偏差为5%,回收率平均值为104%,检测下限为0.036μg/L。约5年的实践检验说明,改进后的方法可满足实际尿样的分析要求。     

铍环电子束焊接温度场和应力场的有限元分析

采用ADINA/ADINAT对铍环电子束焊接过程的温度场和应力场进行了有限元分析 ,结果表明 :铍环焊接过程中焊缝外表面最高温度达 2 73 4℃ ,内表面最高温度仅 3 78℃ ,位于外止口铍钚一侧 ;铍环电子束焊接后 ,在焊缝附近 2 0mm范围内焊接残余应力较大 ,焊缝处于复杂的三维应力状态 ,焊缝根部的残余应力达到最大 ;内外止口铍环由于结构差异 ,焊接残余应力分布并不完全相同。     

Determination of Trace Neptunium in Environmental Samples by ICP-MS

237Nphasbeentraditionaldeterminedbyalphaspectrometryandneutronactivationana-lysis(NAA).Butthesemethodshavesomedisadvantages.Forinstance,α-spectrometryde-mandsahigherdegreeorradiochemicalpurityof237Nptoavoidinterferencefrom234U,231Paand230Th.Itneedsthepre…     

Statistical Estimation of Distributions of Physical Quantities in Nuclear Fission

Making use of a model based on the statistical theory, calculations were performed to obtain the mass yields, the most probable charges, the kinetic energies and the prompt neutron yields of fission fragments, and the mass yields of fission products from thermal-neutron-induced fission of ²³³U, ²³⁵U, ²³⁹Pu, ²⁴¹Pu and from the spontaneous fission of ²⁵²Cf. The calculations are further extended to fast-neutron-induced fission. The scission-point distance is treated as a parameter varying with the mass number of the heavy fragments of fission. This proved successful in approaching the calculated curves closer to the observed values.

It is possible to predict unknown physical quantities in nuclear fission with use made of the method developed in the present work.     

特征荧光X射线吸收法精确测定基于铍膜的235U裂变靶厚度

研究发展了一种基于特征荧光X射线吸收谱的、可精确测量裂变物质质量厚度的方法,系统分析了测量不确定度。实验结果表明,该方法可有效测定基于铍膜的²³⁵U裂变靶质量厚度,测量不确定度小于5%,其不确定度主要来源于测量的统计性。