伏打电堆工作原理争论的发展及启示

针对伏打电堆中产生的电是源于2种不同金属的相互接触还是源于化学反应这一问题,科学家们分别提出了“接触说”和“化学说”2种理论,2种理论经过近半个世纪的争论至融合。通过对这段化学史的回顾,结合现代理论,有利于深入理解电化学主题及其相关核心概念。     

全钒液流电池的隔膜研究与应用

研究全钒液流电池的质子传导膜制备过程,提出高分子亲水/疏水相互作用诱导溶液相分离的成膜原理,进行制膜工艺放大,满足全钒液流电池的电堆制造与储能工程应用需要. 突破现有“离子交换”传质机理的限制,利用电解液中不同价态钒离子与氢离子相比,存在体积和荷电量的差异,通过离子“筛分”和“静电排斥”效应进行离子选择性渗透. 制成孔径分布在4 ~ 7 nm的聚偏氟乙烯质子传导膜,电导率为3.5×10-2 S•cm^-1,爆破强度高于0.3 MPa,面积800 mm × 900 mm. 利用扩散实验测定膜对H⁺/VO²⁺离子选择性,选择性系数达到306. 利用该质子传导膜组装的15 kW电堆,充电/放电循环性能稳定,电流密度达到100 mA•cm^-2,在700多个循环过程电流效率为93%,能量效率超过72%,具备产业化应用前景.     

核燃料后处理技术发展及其放射化学问题

从化学分离手段的改进、后处理的对象变化、与分离功能的拓展等方面较为系统地阐述了核燃料后处理技术发展过程及技术特点;以先进核能系统中分离嬗变为目标,概括总结了从第二代后处理技术向第三代和第四代后处理技术发展过程中Purex流程、后续的分离工艺与处理快堆元件的干法后处理工艺中的主要放射化学问题。     

基于真实情境的初中化学微项目教学实践与反思*——以“溶液的形成”为例

以“溶液的形成”为例进行微项目教学实践,选择学生熟悉的护手霜为主题情境,巧妙设计了“原料分散”“微观探秘”“辨识活动”“对比实验”“感知乳化”等系列微项目活动,通过情境不断地设置认知冲突,引导学生反思、修正并最终形成更完善的概念,在环环相扣的探究活动中使学生自主建构结构化的知识。通过制作“护手霜”将“溶解”和“乳化”串联,感知溶液,感受乳化,感悟人与自然、社会的和谐、可持续发展。     

化学能转化成电能的实验设计

以常见的铜锌原电池反应为例,设计了一组对比实验装置,即化学反应装置与原电池装置。以化学反应装置中的能量变化为依据,展示了化学反应中释放出的能量具体形式为“热”与“功”;通过与原电池装置的比较,证明原电池实验装置中的“热”转化为了电能。     

新建本科院校实验室建设与管理的现状分析

分析了新建本科院校实验室在建设与管理方面存在的问题,指出了制约实验室健康运行的主要障碍为：实验室建设缺乏整体规划;实验室管理不规范;实验队伍建设不科学等。针对以上问题,结合我校在转制升本后采取的思路,指出更新高等教育理念,加强顶层设计,通过“总体规划、合理设置、基础优先、立项建设”等原则进行规划;通过“建章立制、分级管理、及时跟踪、以人为本”的原则进行科学管理,从而保障实验室的健康可持续发展,为实现新时期“中国梦”的人才培养搭建平台。     

开启新一代的科学教育——美国《K-12年级科学教育框架》述评

美国国家研究理事会于2011年7月发布了《K-12年级科学教育框架》,为开启美国新一代的科学教育奠定基础。《框架》采用“核心学科概念”“交叉观念”和“科学与工程实践”3大维度来建构其结构,将“工程与技术、科学应用”纳入核心学科领域,突出科学的实践本质,并通过“学习进程”来描述科学学习的发展过程。通过对《框架》的解读,开拓我国科学教育改革的视野。     

染料敏化太阳能电池中染料分子共轭π桥的扩展

以染料分子D5为原型, 采用不同类型和数量的共轭桥单元来设计D-π-A 型有机分子. 采用密度泛函理论(DFT)和含时密度泛函理论(TDDFT)来模拟计算分子的形貌、分子轨道能级以及紫外-可见光谱, 为染料敏化太阳能电池(DSSCs)的敏化分子寻找适合的共轭桥. 采用“次甲基链”、“呋喃环”或“噻吩环”、“次甲基链和呋喃环”或“次甲基链和噻吩环”作为共轭桥单元, 使得分子的吸收光谱依次红移. 随着共轭桥单元的增加, 分子的吸收光谱有剧烈的红移, 但随着共轭桥单元数量的进一步增加, 分子吸收光谱的红移现象减弱. 分子的最低未占据分子轨道(LUMO)能级逐渐降低, 而最高占据分子轨道(HOMO)能级逐渐升高. 采用3个“次甲基链和呋喃环”或者“次甲基链和噻吩环”作为共轭桥时, HOMO能级已经高于氧化还原电解质的能级, 而在极性溶液中, 由2个“次甲基链和噻吩环”单元作为有机分子的共轭桥时, 分子的HOMO能级已经高于氧化还原电解质的能级了. 采用“次甲基链和呋喃环”或“次甲基链和噻吩环”单元作为有机分子的共轭桥时, 吸收光谱有明显的红移,但对于DSSCs的敏化分子, 这样的共轭桥单元只能有1-2个, 不宜过多.     

火焰原子吸收光谱法测定铀钼合金中镉量

铀钼合金燃料是试验堆用核燃料,具有铀密度高、γ相较稳定、辐照性能优良和后处理简单等优点,是国际上正在大力开发的新一代低浓化核燃料。要保证铀钼合金的核性能和力学性能,对它的化学成分必须控制在技术要求之中;镉因具有很高的中     

静电纺丝制备多级结构TiO2微纳米纤维

通过对共轴电纺内流体溶液浓度和流速的调控得到4种具有不同内部结构的TiO₂微纳米纤维, 即具有“微孔”、“囊泡”、“竹节”和“管”状结构的TiO₂微纳米纤维, 实现了对纤维内部结构的有效控制, 对于新型仿生中空纤维的研究具有重要意义.     

电感耦合等离子体质谱(ICP-MS)及其联用技术在核工业领域的应用进展

综述了电感耦合等离子体质谱(ICP-MS)及其联用分析技术的进展,论述了其在相关核工业及环境领域中分析痕量或超痕量的放射性同位素、长寿命核素、元素形态等的应用。讨论了电感耦合等离子体质谱及联用技术的发展趋势,并对目前存在的主要问题及可能的解决方案进行了讨论。     

Resourceability on nuclear fuel cycle by transmutation approach

A resourceability on nuclear fuel cycle by transmutation of fission products in the spent fuel of nuclear reactors is discussed in this paper to investigate the feasibility of "creation and utilization" of Après ORIENT from Adv.-ORIENT cycle,in which chemical "separation and utilization" of nuclear rare metals(platinum group metals,Mo,Tc,rare earth,etc.) has been proposed since FY2006.Après ORIENT research program was newly initiated in FY2011 for nuclear transmutation of fission products into stable or short-lived highly-valuable elements.In the resourceability of rare earth metals from fission products,non-radioactive Nd and Dy can be created from Pr and Tb,respectively,by transmutation.Especially,the Dy creation has a relatively high feasibility of about 10-20 %/y in creation rate.A proper moderation of neutrons in blanket of fast reactors may be required to provide a high creation rate of La from Ba.In light platinum group metals,non-radioactive Ru can be created from Tc by transmutation,of which creation rate is about 4-5 %/y in blanket of fast reactors.Pd created from Rh is almost non-radioactively depending on the isotope fraction of 107 Pd.Rh creation from Ru is not feasible under the neutron irradiation of typical nuclear reactors.     

Xas study of actinide solvent extraction compounds. ii: UO(NO)(L) (with L=tri-isobutylphosphate, tri-n-butylphosphate, trimethylphosphate and triphenylphosphate)

In the back-end of the nuclear fuel cycle, liquid–liquid extraction is the selected separation method. For an improved design of new extracting agent, the knowledge of the coordination polyhedra of the metal ions is important. In this paper, we investigated the coordination sphere of a series of uranyl complexes with selected organophosphorus extracting molecules: UO₂(NO₃)₂L₂ (with L=tri-iso-butylphosphate, tri-n-butylphosphate, trimethylphosphate and triphenylphosphate) using X-ray absorption spectroscopy. FEFF7 calculations of the EXAFS spectra corresponding to the model compound UO₂(NO₃)₂(TiBP)₂ (with TiBP=tri-iso-butylphosphate) for which the crystal structure is known led to a multiple scattering approach of the data fitting. EXAFS results show subtle U–O(P) bond distance differences between the different complexes that are discussed in terms of both electronic and steric effects of L. These results are discussed with regards to the extraction ability of L. In the same time, exploratory work has been attempted in order to evaluate U–O–P bond angle variations as a function of L using multiple photon-scattering paths. Satisfactory values have been obtained compared to the crystallographic data.     

燃料电池技术在电催化反应领域的应用

燃料电池反应器是一种既能生产有价值化学品,又能同时发电的新型单元操作装置.由于其安全、反应易受控制、无污染,且能源资源利用率高的特点,日益受到各国工业部门的重视.本文评述了几类燃料电池反应器如酸性燃料电池、质子交换膜燃料电池和固体氧化物燃料电池的用途、工作原理及其实现工业化所面临的几个主要问题。     

纳米材料与纳米技术在先进核能系统中的应用前瞻

随着人类对核能需求的快速增长,为应对核能发展的挑战,世界主要核能国家已经开始了先进核能系统的研发。新材料与新技术被认为将在未来先进核能系统中发挥重要作用,其中纳米材料与纳米技术显示了在未来核能中广泛的潜在应用前景。纳米材料是近年来受到广泛重视的一种新型功能材料,本文综述了纳米材料与纳米技术在先进核燃料制造、乏燃料后处理、核废物处置以及核环境修复等核燃料循环领域的应用基础研究现状,并对纳米材料技术在未来先进核能系统中的应用发展趋势进行了展望。     

VHTR,ADS, and PWR Spent Nuclear Fuel Analysis

The aim of this study is to analyze and compare the discharged-spent fuel of three types of nuclear systems: a Very High-Temperature Gas Reactor (VHTR), a lead-cooled Accelerator-Driven System (ADS) and a standard Pressurized Water Reactor (PWR). The two first systems, VHTR, and ADS were designed to use reprocessed fuels. UREX+ and GANEX techniques were used for the reprocessing processes respectively. The fuel burnup simulated for the systems in other works have been used to obtain the final composition of the spent fuel discharged. After discharge, the radioactivity, the radiotoxicity, and the decay heat were evaluated through the ORIGEN 2.1 code until 10⁷ years and compared to the literature.     

A new thermochemical splitting cycle of sodium chloride for chlorine and sodium hydroxide production

A new thermochemical closed cycle of sodium chloride for the preparation of chlorine and sodium hydroxide is presented in this paper. The optimum conditions of the main reactions in the cycle were obtained from a series of experimental results. The heat flow of the cycle system was calculated based on the related thermodynamic equations and data. The kinetic study of the heterogeneous reaction in the cycle was carried out by means of a thermogravimetric method. The result shows that the proposed cycle demonstrates an obviously energy-saving advantage over all the other methods of chlorine and sodium hydroxide productions. It may become economically competitive with the current electrolytic method in the future.     

Inorganic Sol-Gel Preparation of Medium Sized Microparticles of Li2TiO3 from TiCl4 as Tritium Breeding Material for Fusion Reactors

Microspheres of Li₂TiO₃ were fabricated by a classical, inorganic sol-gel process from commercially available TiCl₄. Elaborated process consists of the following main steps: (1) dissolving of TiCl₄ in concentrated aqueous HCl and addition of LiOH; (2) formation of sol emulsion in 2-ethylhexanol-1 containing the surfactant SPAN-80 (EH); (3) gelation of emulsion drops by extraction of water with partially dehydrated EH; (4) impregnation of gel to Li:Ti molar ratio MR = 2; (5) thermal treatment at 1200°C in order to receive chloride free product. This temperature can be significantly lowered (to 750°C) by dechlorination starting solution TiCl₄ by chemical treatment of the with nitric acid to form of nitrate-stabilized titania sols. Tritium release from sol-gel made Li₂TiO₃ microspheres were found very close to that observed for other traditional materials, however for the first sample process starts slightly earlier.     

Thermodynamic functions for U0.45Pu0.55N

Enthalpy increments of U_0.45Pu_0.55N were measured in the temperature range of 1025–1775 K by inverse drop calorimetry using a high temperature differential calorimeter. The enthalpy increments were fitted to a polynomial in temperature and the heat capacity, entropy and Gibbs energy functions were computed. The results are presented and discussed in comparison with literature data.     

核化学与放射化学的研究进展

在我国核能快速发展的新形势下,新型核能资源的开发、乏燃料后处理、放射性废物处理与处置等核燃料循环化学研究日益活跃。随着科学技术的不断发展,离子加速器、反应堆、各种类型的探测器和分析设备、以及计算机技术等的发展,核化学与放射化学研究的范围和成果在不断扩展和增加,如核安全、环境放射化学、放射分析化学、放射性药物与标记化合物等,研究成果对于国防建设、核能发展、核技术应用等方面具有重要支撑作用。本文综述了近年来国内在上述领域所取得的研究进展。共引用参考文献161篇。