非水溶液盐效应的气液色谱研究——非电解质(烃、芳烃、氯代烃、酮)+盐(NaI、NaSCN、KSCN)+碳酸丙烯酯体系

由于碳酸丙烯酯(PC)具有较宽的液相区间(mp:224.0K,bp:514.9K)、较高的介电常数(64.92,298.15K)和较大的偶极矩(4.94D),它是一个在工业和科学研究中有广泛应用的非质子型极性溶剂。已有大量文献就PC溶液中电解质-PC、非电解质-PC和离子-离子间的相互作用情况作了报导。对于非电解质-电解质-PC三元系中溶质-溶剂间的相互作用情况还缺乏了解。本文希望通过测定非电解质溶质在PC的电解质溶液中的无限稀释活度系数γ_1~∞,对非水溶液中的溶质-溶剂作用情况有新的了解。气液色谱法(CLC)是测定无限稀释溶液活度系数的有效方法之一。作者曾利用GLC测定了一些烃、氯代烃、醇、酮在环丁砜电解质溶液中的无限稀释活度系数和盐效应常数.     

233U和武器级钚的爆炸产物放射性衰变过程的比较

对233U模型和武器级钚模型核爆炸后爆炸产物的放射性活度、生物潜在危害因子和能量沉积等量进行了比较 ,分析了武器级钚模型中上述各量的演化情况. Comparison on the nuclear explosive products ’ radioactivity, biological hazard potential, energy deposition after nuclear explosion between the model of 233 U and the model of weapon grade plutonium was made. The detail analysis of the process of above physics quantities in the model of weapon grade Plutonium was also given.     

用电势法测定混合电解质NaCl-Me4NCl-H2O体系在298．15K的活度系数

用电势法测定混合电解质ＮａＣｌ－Ｍｅ_４ＮＣｌ－Ｈ_２Ｏ体系在２９８．１５Ｋ的活度系数阎卫东,姚加,韩世钧,徐奕瑾（浙江大学化学系,杭州,３１００２７）关键词含季铵盐混合电解质,活度系数,渗透系数作为电解质溶液热力学研究工作［１］的继续,本文选择了含季...     

NaCl在CH~3OH-H~2O混合溶剂中活度系数的测定(298.15K)

用电动势法测定了298.15K时,由Na^+和Cl^-离子选择电极组成的电池在NaCl-CH~3OH-H~2O混合体系中的电动势,用扩展的Debye-huckel方程和Pitzer方程关联不同溶剂组成下电动势的实验值,得到电池的标准电动势能和NaCl 在混合溶剂中的活度系数.将Pitzer-Simonson方程应用于含离子缔合体系.求出NaCl 在混合溶剂中的缔合常数,结果表明NaCl在甲醇含量为60%时,可能已有离子对生成     

单个离子标准迁移自由能的测定

本文采用活化分析法测定参考解质Ph4AsPh4B晶体在水和有机溶剂中的溶解度和计算了它从水迁移到有机溶剂中的标准迁移Gibbs自由能△^s^wG^0t.根据Ph4AsPh4B假定,求得参考正负离子Ph4As^+和Ph4B^-的标准迁移Gibbs自由能.又通过测定Ph4AsTcO4,CsPh4B,KPh4B和CsTCO4等晶体在水和有机溶剂站的溶解度,求得TcO4^-,K^+,Cs^+等离子的标准迁移自由能,并对结果进行了讨论.     

气液色谱法研究二元混合固定液的无限稀活度系数

用气液色谱法测定若干烃类溶质在二元混合固定液中的无限稀活度系数,所研究的二元混合液为具有不同极性的四种类型:(1)正廿二烷-正十六烷;(2)邻苯二甲酸二壬酯-角鲨烷;(3)环丁砜-碳酸丙烯酯;(4)环丁砜-己二腈。用最小二乘法拟合三元系的Flory-Huggins公式,得到各种相互作用参数。     

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.     

氧化还原平衡处理的新方法

引入一个假想的水合电子活度的负对数 (pe)的概念 ,使氧化还原平衡和氧化还原滴定的处理得以简化 ,推导出林邦式误差公式 ,使得 4类滴定方法的统一处理更加完善     

CFETR 堆体活化计算与分析

运用FLUKA计算程序对中国聚变工程实验堆(CFETR)进行了一维模拟活化运算,得出了产氚包层、屏蔽层、真空室结构材料、环向场线圈等模块的中子活化特性。计算结果表明,在聚变堆以200MW聚变功率持续稳态运行一年后,刚停堆时堆体的总活度为1.05×10 ¹⁹ Bq,停堆十年后堆体总活度为1.03×10 ¹⁷ Bq,此时堆体的主要残留放射性核素为⁵⁵ Fe。研究结果表明,目前CFETR的设计不存在突出的放射性环境安全问题。     

HIAF高能辐照终端感生放射性

本工作是基于蒙特卡罗模拟软件FLUKA对高能强流重离子加速器（HIAF）高能辐照终端感生放射性进行初步研究。该终端可运行质子最高能量为9.3 GeV,最大流强是1.45×1012 pps（particle per second）。研究内容包括:（1）预测高能辐照终端内活化物质的放射性活度特性;（2）预测不同冷却时间高能辐照终端内残余剂量率分布。研究结果表明,HIAF正常运行时高能辐照终端内的感生放射性主要受束流垃圾桶活化产生的放射性核素影响。当加速器连续运行100天冷却4小时,垃圾桶表面残余剂量率为2.375 mSv·h-1。终端内空气中13N和15O动态饱和比浓度大于其对应的导出空气浓度。冷却水中13N和15O的活度大于对应的ALI_min。该研究是HIAF辐射防护基础研究以及加速器环境影响评价的一项重要内容。The Monte Carlo code FLUKA was used to predict the induced radioactivity of high-energy irradiation terminal of HIAF. The maximum energy of proton is 9.3 GeV, and the maximum current is 1.45×1012 pps (particle per second). In this study we were to predict:(1) the activity properties of activated substances in the experimental terminal; (2) the residual dose rate distribution in the experimental terminal at different cooling time. The results indicate that the induced radioactivity in the high energy irradiation terminal of the HIAF is mainly affected by the radionuclide induced in the beam dump. The residual dose rate on the surface of the beam dump is 2.375 mSv·h-1, after 100 d irradiation and 4 h cooling. The dynamic saturation ratio of 13N and 15O induced in the air inside the terminal is higher than its corresponding derived air concentration. The activity of 13 N and15O induced in cooling water is higher than its ALI_min. This study is a part of radiation protection basic research and environmental impact assessment for HIAF.