PACIFIC - Providing a Nuclear Fuel Cycle in the UK for Implementing Carbon Reductions

太平洋 - 在英国提供核燃料循环以实现碳减排

• 批准号: EP/L018616/1
• 负责人: Timothy Abram
• 金额: $ 389.13万
• 依托单位: University of Manchester
• 依托单位国家: 英国
• 项目类别: Research Grant
• 财政年份: 2014
• 资助国家: 英国
• 起止时间: 2014 至 无数据
• 项目状态: 已结题
• 来源: https://gtr.ukri.org/projects?ref=EP%2FL018616%2F1
• 关键词: PACIFIC; Providing; Nuclear; Fuel; Cycle

PACIFIC is a multi-discipline programme, across 12 UK universities, that supports a future nuclear fuel cycle in the UK. We aim to provide a world-class programme of relevant research into the manufacture, performance, and recycle of current and advanced nuclear fuels. For the first time in a major UK academic research programme, we will integrate the two Themes of Nuclear Fuel and Separations Technology into a single programme with a common goal. In the Fuels Theme, our aim is to provide a scientific and technological underpinning to understanding the damage mechanisms that occur in nuclear fuel and cladding materials throughout their operational life and during storage. Our objectives are to:1. extend molecular dynamics models to predict key properties of advanced fuels;2. identify promising single component and composite materials for advanced fuels and to develop appropriate manufacturing routes.;3. investigate the potential for improved TRISO coated fuel particles by employing a duel SiC/ZrC layer;4. assess the performance of advanced fuels and coatings under a range of conditions; and5. investigate the mechanism of Pellet-Cladding Interaction failures in LWRs.The first Fuels project addresses advanced fuels and coatings. This Project will employ a combination of advanced modelling and experimental techniques to identify promising new fuel materials, and to explore the mechanisms and effects of radiation damage in both current and advanced fuel materials, including coated fuel particles. Specific Tasks include:- Fuel Modelling- Advanced Fuel Manufacture- Advanced TRISO Coated Fuel Particles- Materials Characterisation and IrradiationThe second Fuels project concerns a failure mechanism known as Pellet-Cladding Interaction (PCI). This project will focus on developing a mechanistic understanding of PCI by bringing together metallurgical, mechanical engineering, chemical and radiation aspects; by a combination of experimental investigations and underpinned by computer simulation.In the Separations theme, the projects aim to provide a proof of concept for an integrated flowsheet capable of providing a product suitable for fast reactor fuels from a thermal fuel feed. Our objectives are to:1. Prove that U, Pu and MAs can be separated to the required purities and in a mixed product for conversion to fast reactor fuel.2. Prove that the liquid product from a hydrometallurgical separation process can be converted to the required form for fast reactor fuel manufacture.3. Prove that a new hydrometallurgical separation process can operate within current solvent extraction technologies.4. Prove that new technologies are available that will offer benefits over current solvent extraction technologies.The project on Minor Actinide Separations will investigate new hydrophobic extractants use in separation of MAs from lanthanides, group actinide separations and Am/Cm separations. Specific Tasks include: - Direct Monitoring of Speciation in Minor Actinide Separations- Optimising Interfacial Transfer Kinetics during Minor Actinide Separations- Actinide Behaviour and Radiolysis Effects of Complexants in Minor Actinide Separations- Ligand Structure-Activity Relationship DevelopmentThe project on Advanced Separations Technology includes the following tasks: - Develop a better understanding of conventional solvent extraction technology - High efficiency extractions using intensified processes- Continuous Chromatographic Separation of Actinides and Fission ProductsThe final project concerns Product Conversion to Fuel, and will develop the fundamental molten salt technology to take the product from a PUREX plant and convert it efficiently through direct reduction to metal, considering proliferation resistance and waste minimisation. Tasks include:- Establishment and optimisation of the process for direct reduction of spent fuel- Decontamination and immobilisation of pyroprocessing wastes.

Pacific是一项多学科计划，遍布英国12所大学，该计划支持英国未来的核燃料周期。我们旨在为当前和先进的核燃料的制造，性能和回收利用提供世界一流的研究计划。在英国主要的学术研究计划中，我们将第一次将核燃料和分离技术的两个主题整合到一个具有共同目标的单个计划中。在Fuels主题中，我们的目标是提供科学和技术的基础，以了解整个运营生活和存储期间核燃料和覆层材料中发生的损害机制。我们的目标是：1。扩展分子动力学模型以预测晚期燃料的关键特性； 2。确定有希望的单一组件和复合材料，用于高级燃料并开发适当的制造路线。3。通过采用决斗SIC/ZRC层来研究改善Triso涂层燃料颗粒的潜力； 4。评估在各种条件下的高级燃料和涂料的性能；和5。研究LWR中的固定相互作用失败的机制。第一个燃料项目解决了高级燃料和涂料。该项目将采用先进的建模和实验技术的组合来识别有希望的新燃料材料，并探索当前和先进的燃料材料（包括涂层燃料颗粒）中辐射损伤的机制和影响。特定任务包括： - 燃料模量 - 先进的燃料制造 - 高级Triso涂层燃料颗粒 - 材料表征和辐射第二燃料项目涉及一种被称为固定固定相互作用（PCI）的故障机制。该项目将着重于通过将冶金，机械工程，化学和辐射方面汇总在一起来发展对PCI的机械理解。通过实验研究和由计算机模拟的基础的结合。在“分离主题”中，这些项目旨在为综合流程图提供概念验证，以便能够提供适用于热燃料饲料的快速反应器燃料的产品。我们的目标是：1。证明U，PU和MAS可以分离到所需的纯度中，并在混合产品中分开，以转换为快速反应堆燃料2。证明可以将水膜分离过程中的液体产物转换为快速反应堆燃料制造所需的形式。3。证明在当前溶剂提取技术中可以进行新的水透明分离过程。4。证明有新技术将为当前的溶剂提取技术提供优势。次要肌动蛋白分离的项目将研究新的疏水提取物在将MAS与Lanthanides分离，组actacinide分离和AM/CM分离中使用。具体任务包括： - 在少量actacinide分离过程中优化次要肌动剂分离中的物种动力学的直接监测 - 在少量actacinide分离中的actacinide行为和辐射效应的界面转移动力学 - 结构分离 - 结构 - 效应关系的发展 - 高级分离技术的项目 - 使用以下任务更好地理解传统的渗透效率，以更好地理解传统的渗透效率， Actinides和Fission产品最终项目涉及产品转换为燃料，并将开发基本的熔融盐技术，以从Purex工厂从Purex植物中夺取产品，并通过直接减少将其直接减少为金属，考虑到增殖耐药性和浪费最小化。任务包括： - 建立和优化直接减少用过的燃料净化和固定式燃气废料的过程。

项目成果

Characterisation of electrodeposited polycrystalline uranium dioxide thin films on nickel foil for industrial applications

• DOI: 10.1016/j.tsf.2015.11.030
• 发表时间: 2015-12
• 期刊: Thin Solid Films
• 影响因子: 2.1
• 作者: A. Adamska;E. L. Bright;J. E. Sutcliffe;Weiru Liu;O. Payton;L. Picco;T. Scott

Electrochemical Reduction of Tungsten Oxide in LiCl-KCl Molten Salt Eutectic using the Fluidised Cathode Process

• DOI: 10.1016/j.electacta.2016.12.114
• 发表时间: 2017-02
• 期刊: Electrochimica Acta
• 影响因子: 6.6
• 作者: R. Abdulaziz;L. Brown;D. Inman;P. Shearing;D. Brett

Separation of Am(III), Cm(III) and Eu(III) by electro-spun polystyrene-immobilized CyMe4-BTPhen

• DOI: 10.1016/j.tet.2018.04.037
• 发表时间: 2018-09
• 期刊: Tetrahedron
• 影响因子: 2.1
• 作者: A. Afsar;James Westwood;Petr Distler;L. Harwood;Saeed D. Mohan;J. John;F. Davis

The Role of Kinetics in Advanced Nuclear Fuel Reprocessing

动力学在先进核燃料后处理中的作用

• 发表时间: 2022
• 作者: A. Jackson

Electrochemical Reduction of UO 2 to U in LiCl-KCl Molten Salt Eutectic Using the Fluidized Cathode Process

采用流化阴极工艺将 LiCl-KCl 熔盐共晶中的 UO 2 电化学还原为 U

• DOI: 10.1149/07515.0069ecst
• 发表时间: 2016
• 期刊: ECS Transactions
• 作者: Abdulaziz R