间接标记假尿嘧啶核苷方法的研究

本文报告了固相标记假尿嘧啶核方法。用苯乙酸作偶联剂，以巯基树脂为载体，利用硫与汞的高效率结合，对假尿嘧啶核苷进行间接标准（I^125)。最后采用高压液相色谱分离，标记率为40-50%.     

金属氚化物中^3He的热解析行为初步研究

国内外关于金属中氦行为的热解析研究报道尚不多见，特别是关于高固氦合金材料设计、制备、性能快速评价的研究尤为缺乏。本工作从室温到1273K全程线性升温，采用四极质谱计实时测量的方法，研究金属氚化物中^3He的热解析行为。     

真空热解析分析系统的研制

系统主要针对金属材料中氢同位素和氦的热解析研究而研制，系统原理图如图l所示。系统支路中设计消气剂床，用以避免金属氚化物解析时氚的排放问题；温度、压力和解析组分等由采集系统采集与分析。     

铀床氚残留量的测量

分别采用直接测量法、同位素交换法和溶解法测量铀床中的氚残留量, 并分析了这三种测量方法在本实验条件下的误差. 直接测量法测量铀床的氚残留量的结果如下: 铀床的氚残留量为2.68%, 即每克铀含(0.0308±0.0003) mmol 氚气; 当压力读数在1500～133332 Pa之间时, 基于理想气体状态方程的测量方法(简称PVT法)的标准差小于0.95%. 同位素交换法测量铀床氚的结果如下: 加热充分解吸过的铀床经多次同位素交换后, 其交换效率仅为2.84%, 即不到3%(摩尔分数)的氚被氘气载带出来, 其同位素交换法测量的标准差为7.35%. 溶解法能够彻底地测量铀床中残留的氚, 其溶解法测量的标准差为6.49%.     

LaNi4．25Al0．75合金吸放氚性能

在真空系统中对熔融法制备的LaNi4.25Al0.75合金的氘活化特性、吸放氚p-C-T曲线和不同温度下的吸放氚速率，以及材料吸附氚气与解析氚气的纯度进行了研究，以考核该合金氚操作与贮存性能。     

二项指数法修正静态热解析系统压力测量误差

热解析技术是目前研究热解析动力学，决定吸附热、表面反应阶数、吸附状态数和晶面吸附分子浓度的最广泛使用的技术。热解析系统样品室程序升温导致系统内气体温度不均匀，必然引起材料解析出气体压力测量的误差。采用二项指数法对这一误差进行了修正。     

Microstructure and Mechanical Properties of Ti3SiC2 Irradiated by Carbon Ions

Thanks to its noteworthy mechanical properties, excellent damage tolerance and good thermal stability, the Ti3SiC2 ternary compound has attracted great concern and has been considered as a potential structural component material for the 4th generation of reactors （e.g., gas fast nuclear reactors） and future fusion reactors. The outstanding properties are due to the nanolameIlar structure which imparts characteristics of both metals and ceramics to this material In our work, Ti3SiC2 samples have been irradiated by C^＋ ions with a high fluence of 1.78 × 10^17 ions/cm^2 at a range of temperatures from 120℃～850℃. Subsequently, series of characterization techniques including synchrotron irradiation x-ray diffraction, scanning electron microscopy and nano-indentation are carried out to understand the changes of microstructure and mechanical properties. The composition exhibits high damage tolerant properties and a high recovery rate through the analysis, especially at high temperature. The minimum damage to an irradiated sample appears around 350℃ in the temperature range 120℃-550℃. At a high irradiation temperature, a significant reduction in the damage can be achieved and an almost complete lack of damage compared with an un-irradiated sample is revealed at the temperature of 850℃.     

Diffusion behavior of helium in titanium and the effect of grain boundaries revealed by molecular dynamics simulation

The microstructures of titanium(Ti), an attractive tritium(T) storage material, will affect the evolution process of the retained helium(He). Understanding the diffusion behavior of He at the atomic scale is crucial for the mechanism of material degradation. The novel diffusion behavior of He has been reported by molecular dynamics(MD) simulation for the bulk hcp-Ti system and the system with grain boundary(GB). It is observed that the diffusion of He in the bulk hcp-Ti is significantly anisotropic(the diffusion coefficient of the [0001] direction is higher than that of the basal plane),as represented by the different migration energies. Different from convention, the GB accelerates the diffusion of He in one direction but not in the other. It is observed that a twin boundary(TB) can serve as an effective trapped region for He.The TB accelerates diffusion of He in the direction perpendicular to the twinning direction(TD), while it decelerates the diffusion in the TD. This finding is attributable to the change of diffusion path caused by the distortion of the local favorable site for He and the change of its number in the TB region.