The influence of potential on the anodic dissolution of SIMFUEL (UO2)

The influence of potential on the anodic dissolution of SIMFUEL (doped uranium dioxide) has been characterized over the range 0-500 mV (versus SCE). Cathodic stripping voltammetry was used to determine the changes in surface reactivity of UO₂ in neutral solutions after different anodic oxidation timescales. Scanning electron microscopy (SEM) was used to view the damage to the SIMFUEL electrode surface which was minimal at E < 200 mV but present as local pits and eroded grains after oxidation at higher potentials. Long-term anodic oxidation at potentials below 200 mV suggests that local acidification can develop within surface asperities in the fuel and pores in corrosion product deposits accumulated on the electrode surface.     

Geotechnical behavior of uranium mill tailings from Saskatchewan,Canada

This paper investigates the geotechnical behavior of uranium mill tailings from Saskatchewan, Canada.The 4% tailings were well-graded with 29% fines whereas the 5% and 6% tailings were gap-graded with 49% fines. All samples exhibited a negligible strength(0.4 k Pa) up to 60% solids, followed by a rapid increase. The 4% tailings exhibited a lower rate and amount of settlement than 5% and 6% tailings. The kidecreased from 10~(-2)to 10~(-4)m/s with a decrease in eifrom 16 to 4 and a decrease in ef from 8 to 4 such that 4% tailings showed one order of magnitude lower values than the 5% and 6%tailings. The settling potential decreased ten times(50%–5%) for 4% tailings and four times(60%–15%)for 5% and 6% tailings. The effective stress increased from 80 to 260 Pa in the settling tests. The 4%tailings were less prone to segregation when compared with 5% and 6% tailings. The average solids content after settling was 35% for 4% tailings, 40% for 5% tailings and 39% for 6% tailings with a solids content deviation of ±3%, ±8%, ±6%, respectively. All materials were essentially non-segregating at 40%initial solids.     

含铀煅烧渣粉末酸浸工艺条件的研究

本文根据影响含铀煅烧渣粉末酸浸的主要因素：酸浸温度（A）、酸浸酸度（B）、酸浸时间（C）、渣粉粒度（D），采用正交实验法L16（4^4）对其酸浸工艺条件进行了研究：同时也对一次酸浸残渣中铀的再回收技术进行了探讨。实验结果表明：含铀煅烧渣粉末在所试最佳条件下．其浸出率可达97．5％以上．一次酸浸残渣中铀含量〈3％；一次酸浸残渣用浓硫酸熟化、煅烧破碎后．进行第二次酸浸实验，浸出率可达94％以上，二次酸浸残渣中含铀〈0．3％。通过本次实验．为实现大规模处理回收含铀煅烧渣粉末中的金属铀奠定了良好的基础。     

贫化铀的环境污染影响及其对人体健康的危害

贫化铀是铀富集过程中产生的副产品。由于其独特的物理特性,被广泛开发利用到民用和军事用途。“海湾战争综合症”和“巴尔干综合症”引起了人们对贫铀使用后,对环境污染的影响和对人体健康效应研究的重视。贫铀的危害来自化学毒性和放射性毒性两个方面。由于贫铀的放射性比活度低,而且主要发射α粒子,所以来自贫铀的辐射伤害主要是吸入贫铀气溶胶后对肺和其他器官较长时间的内照射。     

对叔丁基杯[4]芳烃乙酸对铀(Ⅵ)的萃取研究

合成了对叔丁基杯「４」芳烃及其衍生物对叔丁基杯「４」芳烃乙酸,研究了对叔丁基杯「４」芳烃乙酸对铀酰离子的萃取。测定了不同酸度和不同萃取剂浓度对分配比的影响。确定其萃合物组成为ＵＯ２Ｈ２Ｌ。求出了萃取反应平衡常数,讨论了萃取机理。     

铀富集厂容器取料过程中的核临界安全计算

介绍了在中国核工业集团公司兰州铀浓缩厂的核燃料生产中，针对某容器取料过程中存在的核临界安全问题，采用蒙特卡罗方法KENOⅥ程序进行的计算。通过计算表明，某容器在取料过程中，在保护杯起作用的情况下，是可以保证临界安全的，从而解决了该厂核燃料生产中，某容器取料过程的核临界安全问题。     

激光荧光法测定尿和环境样品中的微量铀

本文描述了用 UA-3铀分析仪——激光荧光法测定尿和各类环境样品中的微量铀。实验证明,样品经处理后,能很好地适于用 UA-3对铀的测量。并对多种样品中的铀进行了测定与比对。     

Potable water recovery from As, U, and F contaminated ground waters by direct contact membrane distillation process

In this study, the feasibility of the direct contact membrane distillation (DCMD) process to recover arsenic, uranium and fluoride contaminated saline ground waters was investigated. Two types of membranes (polypropylene, PP; and polytetrafluoroethylene, PTFE) were tested to compare the permeate production rates and contaminant removal efficiencies. Several experiments were conducted to study the effect of salts, arsenic, fluoride and uranium concentrations (synthetic brackish water with salts: 1000-10,000 ppm; arsenic and uranium: 10-400 ppb; fluoride: 1-30 ppm) on the desalination efficiency. The effect of process variables such as feed flow rate, feed temperature and pore size was studied. The experimental results proved that the DCMD process is able to achieve over 99% rejection of the salts, arsenic, fluoride and uranium contaminants and produced a high quality permeate suitable for many beneficial uses. The ability to utilize the low grade heat sources makes the DCMD process a viable option to recover potable water from a variety of impaired ground waters.     

金属及金属氧化物掺杂改性二氧化铀燃料的研究进展

随着商用反应堆对长周期、高燃耗需求的日益提升,燃料芯块将面临更加严苛的服役条件。如何进一步提高二氧化铀燃料的物理化学性能是开发新型核燃料元件亟待解决的关键技术问题。本文基于近年来在掺杂燃料芯块领域最新研究进展,系统总结并讨论了掺杂元素类型及其对二氧化铀燃料芯块性能的影响机理,阐述了掺杂燃料微观组织与性能之间的内在联系,指出当前该研究领域仍存在的科学/技术问题以及掺杂二氧化铀的发展趋势,为改善燃料芯块安全性能的设计提供重要的理论参考。