Deposition of UF5 on the surface of steel material having oxide coating in contact with gaseous UF6

When UF6 is handled in leak tight system, the amount of uranium compound formed on the surface of containers, valves, and others in UF6 handling facilities is not so significant for a short term that special attention has not been given to this problem. The present work was done to throw some more light on this problem based on the recent experiment. We discuss the possibility that the intermolecular transfer of a fluorine atom from UF6 to UF5 may participate in the formation of uranium compound. The discussion includes also the unique features contained in the experimental result, the reaction processes assumed in this problem, and the derivation of a rate equation for expressing the deposition of uranium compound. Furthermore, we propose a new method for determining nonlinear parameters included in a governing differential equation having two variables for expressing the deposition of uranium compound from experimental raw data.     

掺杂聚苯胺导电膜的制备及对核设施表面铀的去污

制备了掺杂导电聚苯胺可剥离膜，首次采用涂膜、电解联用去污方法，进行涂膜电解去除渗透到核设施金属材料内部形成氧化物的铀。在膜中，聚苯胺、盐酸、EDTA-2Na含量各为4％、0．5％～1%、1％；电解电压2．3V、电解时间25min～30min时，其去污率可达99％，优于其它的方法。     

HNO3和有机介质中U（Ⅳ）的稳定性研究

研究了ＨＮＯ＿３和ＴＢＰ－煤油介质中Ｕ（Ⅳ）的稳定性。测定了两种介质中Ｕ（Ⅳ）、ＨＮＯ＿３、ＴＢＰ浓度和气相中氧浓度对Ｕ（Ⅳ）氧化速率的影响。Ｕ（Ⅳ）的氧化速率都随温度提高而明显增加．其表观活化能分别为９１ｋＪ／ｍｏｌ（ＨＮＯ＿３介质）和４２ｋＪ／ｍｏｌ（ＴＢＰ－煤油介质）。对两种介质中Ｕ（Ⅳ）的氧化速率规律进行了比较。     

后遥感应用技术的提出与思考

本文在总结遥感技术应用于铀矿地质领域的实践和遥感技术最新进展的基础上。提出后遥感应用技术，并对其技术内涵、研究内容、建立试验样区、研究意义等进行了探讨。     

铀表面初始氧化行为的电子能量损失谱研究

利用俄歇电子能谱仪获取了表面清洁的铀及其在氧化过程中的电子能量损失谱(EELS)，研究这些电子能量损失谱线显示：清洁表面铀的等离子损失的实验值与理论值较为符合；随着氧化程度的加剧，体等离子体(BP)、表面等离子体(SP)以及价带间跃迁所造成的电子能量损失峰发生了明显的连续偏移和强度的变化，表明室温下清洁表面铀暴露微量纯氧后，在铀表面上发生了U→UO→UO2初始氧化过程。同时，又采用了俄歇电子能谱(AES)和X射线光电子谱(XPS)对照分析了铀的初始氧化过程。     

超临界CO2处理后的金属铀表面氧化腐蚀和电化学腐蚀实验研究

采用重量法和电化学方法分别得到表面经超临界CO2处理后的铀试样在60℃、70％RH条件下的氧化动力学曲线(△m-t)和在50μg/g Cl^-溶液中的阳极极化曲线、自腐蚀电流等抗蚀评价指标。结果表明：经超临界CO2处理后，金属铀表面抗氧化腐蚀性能和抗化学介质腐蚀性能均有一定程度提高。对钝化膜提高金属铀表面抗腐蚀性能的原因进行了探讨。     

钍归-化在盆地γ能谱资料处理中的应用

在应用γ能谱资料寻找砂岩型铀矿的过程中，要尽可能地消除非矿化因素引起的干扰，提取与铀矿化有关的信息。介绍了钍归-化的原理及特点，采用与矿化有关的元素迁移信息的钍归-化方法，分析了二连盆地东部的γ能谱资料，揭示了该区放射性元素的分布特征、地球化学作用和后期铀元素的迁移与富集。结合其他地质资料，分析了钾剩差的变异区（正、负高值区）及铀剩差正高值区形成的原因，同时指出了经过钍归-化处理所得到的铀剩差正高值区应为氧化与还原作用过渡带的直接指示，也是该区进一步寻找砂岩型铀矿的重要标志。     

一种简便的饮用水除铀方法及其机理

本文介绍一种利用原水中含有的无机盐,加入廉价的化学试剂除去饮用水中微量铀的简便方法。并对其除铀机理进行了探讨,证明除铀主要是以软化水过程中产生的氢氧化镁表面吸附共沉淀机理进行的。     

Effect of Water Vapor on the Release of Fission Gases from Uranium Oxycarbide in High-Temperature, Gas-Cooled Reactor Coated Fuel Particles

The hydrolysis of uranium oxycarbide (UCO) was studied by injecting water vapor into a fuel element containing a known number of high-temperature, gas-cooled reactor (HTGR) coated particles with exposed fuel kernels. The experiments were conducted in the High Flux Isotope Reactor (HFIR) at temperatures between 700° and 1000°C, a system pressure of 200 kPa, and partial pressures of water vapor between 21 and 199 Pa. The general sequential response of the exposed fuel kernels to water vapor addition consisted of (1) a rapid release of stored fission gas with a concomitant increase in the steady-state release and (2) a period of constant steady-state release. Upon cessation of the addition of water vapor, a decline in the release to prehydrolysis values generally occurred. The release of stored fission gas was dependent on the square of the partial pressure of water vapor. The ratio of the constant steady-state release to the prehydrolysis value was independent of the partial pressure of water vapor. The time constant for the decline in the release was the same in all of the hydrolysis tests.