Performance of structural and fuel materials in molten lead-based fluids
Performance of structural and fuel materials in molten lead-based fluids
批准号:
2625249
负责人:
金额:
$0.0万
依托单位:
依托单位国家:
英国
项目类别:
Studentship
财政年份:
2021
资助国家:
英国
项目状态:
未结题
起止时间:
2021 至 --
中文摘要
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英文摘要
This EPSRC iCase funded PhD studentship is based within the Interface Analysis Centre Research Group in the University of Bristol School of Physics. The project will work in collaboration with the National Nuclear Laboratory and United Kingdom Atomic Energy Authority on the effects of molten lead on materials for advanced fission and fusion energy.Decarbonising the energy sector is critical to achieving net zero. Innovative molten lead-based technologies supporting both fission (reactor coolant) and fusion (breeding blanket) show enormous promise. This PhD addresses significant gaps in scientific and technological understanding of interactions between molten lead and advanced materials. The corrosive conditions in an irradiated lead coolant circuit are highly challenging to conventional materials. The project will undertake materials degradation test work at small scale using a variety of materials and make mechanistic advances to allow prediction and control of corrosion, as well as facilitating development and qualification of new materials. This PhD project will centre around small-scale mechanistic material degradation testing in high temperature molten lead. The student will develop experimental techniques to understand the properties of a number of novel structural materials. The student will also use advanced materials characterisation techniques including scanning and transmission electron microscopy, electron backscatter diffraction, atom probe tomography and high-speed atomic force microscopy. There will be the opportunity for the student to take part in collaborative work with larger scale national facilities.The project is central to the EPSRC energy theme, addressing the materials, fission and fusion research areas. The student will contribute to addressing materials degradation (corrosion) challenges facing advanced nuclear reactor technologies and barriers to application of new materials in these challenging environments.
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