共查询到17条相似文献,搜索用时 62 毫秒
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锂陶瓷氚增殖剂的中子辐照性能与产氚行为 总被引:2,自引:0,他引:2
D-T聚变堆采用氚增殖剂与中子反应生成氚来保证其燃料的“自持”。Li2O、LiAlO2、Li2ZrO3、Li2TiO3和Li4SiO4等锂陶瓷材料由于具有良好的化学稳定性、机械力学性能和产氚性能等优点,是聚变堆主要的候选产氚材料,而其在中子辐照环境下的各种性能和行为是氚增殖包层模块设计所关心的重要内容。本文介绍了国际上锂陶瓷产氚增殖剂的辐照实验研究概况,对材料的辐照性能(材料稳定性、热导性、离子电导性和活化性能等)、堆内/堆外产氚行为、影响氚在陶瓷材料中扩散或释放的各种因素,以及近来关注较多的辐照缺陷与释氚行为的相互关系等方面进行了归纳、分析和总结,同时针对中国确定的氦冷固态球床包层模块的技术路线,提出了需要广泛而系统地开展锂陶瓷基础研究的建议,指出今后国际上氚增殖剂的研究重点是高燃耗(>10%)和高荷载破坏情况下锂陶瓷材料的辐照产氚性能,以及聚变堆氚增殖包层工程条件因素,如磁场、等离子体诱发电流和中子倍增剂等对锂陶瓷小球释氚行为的影响。 相似文献
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最轻的放射性核素——氚的历史,美国化学家利比(W.F.Libby)在诺贝尔奖金获得者的回忆录中,把它分为两个时期,以人类进行的第一次热核武器试验作为分界线。但合理的划分应为三个时期:第一个时期——氚的发现和物理化学特性的测定(1934— 相似文献
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本文介绍了应用液-液催化、氢-氚交换法制备某些氚标记杂环化合物。采用PtO_2作为催化剂,选用含有杂氮原子的、杂氮和杂硫原子的、杂氧原子的十二种化合物作为研究对象,并用~3H NMR研究了氚在这些杂环化合物中的位置以及它在分于中的相对丰度,得到了满意的氚渗入结果。 相似文献
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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%. 相似文献
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介绍了钛材碱洗脱脂除油和酸洗除去氧化皮的原理和方法,重点阐述了钛材碱洗除油和酸洗除去氧化皮的工艺条件、工艺流程和设备. 相似文献
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Agmatine is a promising anti-opioid dependence and relapse drug1~2 discovered and developed by Beijing Institute of Pharmacology and Toxicology, but the physiological role of agmatine in inhibition of tolerance to and dependence on opioid are not well est… 相似文献
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《Analytical letters》2012,45(1):63-70
Abstract A procedure has been developed for the quantitative analysis of potassium for its tritium content. This procedure consists of dissolving the highly reactive alkali metal in an inert liquid containing a small amount of ethanol and then analyzing the resulting solution for its tritium content by classical methods. Techniques previously used for sodium analysis are reviewed and discussed as they apply to the more reactive potassium. 相似文献
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Alessia Santucci Luca Farina Silvano Tosti Antonio Frattolillo 《Molecules (Basel, Switzerland)》2020,25(23)
Non-evaporable getters (NEGs) are metallic compounds of the IV group, particularly titanium and/or zirconium-based alloys and are usually used as pumps in vacuum technologies since they are able to sorb, by chemical reactions, most of the active gas molecules, with particular efficacy towards hydrogen isotopes. This work suggests an alternative application of these materials to fusion nuclear reactors, where there is the need to recover small amount of tritium from the large helium flow rate composing the primary coolant loop. Starting from the tritium mass balance inside the primary coolant loop, the amount of coolant to be routed inside the coolant purification system (CPS) is identified. Then a feasibility study, based on the bulk getter theory, is presented by considering three different commercial alloys, named ST707, ST101 and ZAO. The results provide the mass, the area and the regeneration parameters of the three different alloys necessary to fulfill the requirements of the CPS unit. By comparing the features of the three alloys, the ZAO material appears the most promising for the proposed application because it requires the lower amount of material and a lower number of regeneration cycles. 相似文献