Extraction of hydrogen isotopes from molten lithium

从熔融锂中提取氢同位素

• 批准号: 2764619
• 金额: --
• 依托单位: University of Bristol
• 依托单位国家: 英国
• 项目类别: Studentship
• 财政年份: 2022
• 资助国家: 英国
• 起止时间: 2022 至 无数据
• 项目状态: 未结题
• 来源: https://gtr.ukri.org/projects?ref=studentship-2764619
• 关键词: Extraction; hydrogen; isotopes; molten; lithium

The focus of this PhD is to examine the use of molten lithium in the breeder blanket system is a future nuclear fusion reactors and to investigate a number of the different physio-chemical parameters and phenomenological material behaviours such that the performance of molten lithium inside a fusion reactor's breeder blanket can be well defined.The PhD will examine initially the melting behaviour of lithium containing different concentrations of hydrogen in deuterium (as surrogates for tritium) and will examine the use of gas insertion and vacuum extraction to optimise the extraction of these hydrogen isotopes.The project will also examine the reactivity of molten lithium when exposed to different gases containing oxidising agent such as water vapour, oxygen and nitrogen to understand (i) the gradual degradation of the molten lithium, through oxide and hydroxide formation, (ii) what effect suspended microparticles of oxide and hydroxide have on hydrogen extraction; and (iii) the interaction of lithium with potential breeder blanket wall materials e.g. SiC, Zr, ODS and Eurofer steel.The experimental PhD will be achieved using the glovebox facility for uranium and reactive metals in the Interface Analysis Centre at the University of Bristol, including a glovebox housed thermos-gravimetric analysis system as well as hydrogen gas flow-control rigs with integrated furnaces.The purpose of this PhD is to better define and optimise the extraction of hydrogen isotopes from molten lithium metal. Lithium is well recognised as being an important element for nuclear fusion in that the light isotope lithium-6 is regarded as the primary isotope that can be used for the neutron-based production of tritium - a primary component of fusion fuel.

该博士的重点是检查在繁殖者覆盖系统中使用熔融锂的使用是未来的核融合反应器，并研究了许多不同的生理化学参数和现象学材料行为，使熔融锂在融合反应器的繁殖层中的表现可以很好地定义，可以很好地识别pHD的融合。对于tritium），并将检查气体插入和真空提取以优化这些氢同位素的提取。该项目还将检查熔融锂的反应性，以接触含有氧化剂的不同气体（例如水蒸气，氧气，氧气，氧气和氮气），以理解（i）通过氧化液的逐渐降级，以及氧化液的逐渐降级。氧化物和氢氧化物的微粒在提取氢上具有； （iii）锂与潜在的育种毯壁材料的相互作用，例如SIC，ZR，ODS和EUROFER钢。在布里斯托尔大学的界面分析中心中，将使用用于铀和反应金属的手套箱设施来实现实验性博士学位，其中包括杂物箱中容纳热量的热量测量分析系统，以及与氢气流量的液体流动式液化液相关的液体。 金属。锂被广泛认为是核融合的重要元素，因为光同位素锂6被视为可用于基于中子的tritium的主要同位素 - 融合燃料的主要成分。