权益分类	功能权益	普通用户	{{item.name}}会员
{{category.name}}	{{benefitItem.name}}

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

基本信息

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

项目摘要

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是一个跨12所英国大学的多学科计划，支持英国未来的核燃料循环。我们的目标是提供一个世界级的相关研究计划，以制造，性能和回收当前和先进的核燃料。在英国的主要学术研究计划中，我们将首次将核燃料和分离技术这两个主题整合到一个具有共同目标的单一计划中。在燃料主题中，我们的目标是提供科学和技术基础，以了解核燃料和包壳材料在其整个使用寿命和储存期间发生的损坏机制。我们的目标是：1.扩展分子动力学模型以预测先进燃料的关键特性;2.为先进燃料确定有前途的单组分和复合材料，并开发适当的制造路线。3.研究通过采用双SiC/ZrC层改进TRISO涂覆燃料颗粒的潜力;4.评估先进燃料和涂层在一系列条件下的性能;以及5.研究轻水堆芯块-包壳相互作用失效的机理。第一个燃料项目涉及先进燃料和涂层。该项目将采用先进的建模和实验技术相结合的方法，以确定有希望的新燃料材料，并探索现有和先进燃料材料（包括包覆燃料颗粒）中辐射损害的机制和影响。具体任务包括：-燃料建模-先进的燃料制造-先进的TRISO涂层燃料颗粒-材料表征和辐照第二个燃料项目涉及一种称为芯块-包壳相互作用（PCI）的失效机制。该项目将集中于通过结合冶金、机械工程、化学和辐射方面，结合实验研究和计算机模拟，对PCI进行机理性理解。在分离主题中，该项目旨在为能够从热燃料进料中提供适用于快堆燃料的产品的综合流程图提供概念验证。我们的目标是：1.证明铀、钚和甲基丙烯酸甲酯可以分离到所需的纯度，并在混合产品中转化为快堆燃料。证明湿法冶金分离过程的液体产品可以转化为快堆燃料回收所需的形式。证明一种新的湿法冶金分离工艺可以在现有的溶剂萃取技术下运行.证明新技术的可用性，将提供优于当前溶剂萃取技术的优势。关于次要锕系元素分离的项目将研究用于镧系元素分离MAs，锕系元素分离和Am/Cm分离的新型疏水萃取剂。具体任务包括：- 直接监测次锕系元素分离过程中的形态-优化次锕系元素分离过程中的界面转移动力学-次锕系元素分离过程中的锕系元素行为和配位剂的辐解效应-发展配体结构-活性关系- 更好地了解传统的溶剂萃取技术-使用强化工艺的高效萃取-锕系元素和裂变产物的连续色谱分离最后一个项目涉及将产物转化为燃料，并将开发基础熔盐技术，从PUREX工厂获取产物，并通过直接还原将其有效转化为金属，同时考虑到防扩散和废物最小化。任务包括：-建立和优化直接还原乏燃料的工艺-高温处理废物的去污和固定。

项目成果

期刊论文数量（10）

专著数量（0）

科研奖励数量（0）

会议论文数量（0）

专利数量（0）

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
通讯作者：
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
通讯作者：
R. Abdulaziz;L. Brown;D. Inman;P. Shearing;D. Brett

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

DOI：
发表时间：
2022
期刊：
影响因子：
0
作者：
A. Jackson
通讯作者：
A. Jackson

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
通讯作者：
A. Afsar;James Westwood;Petr Distler;L. Harwood;Saeed D. Mohan;J. John;F. Davis

Process intensification applied to spent nuclear fuel reprocessing: An alternative flowsheet using small channels