Spent nuclear fuel in the U.K. is stored within ponds dosed with NaOH in order to inhibit corrosion and, to ensure the efficiency of storage regimes, there is a need to define and quantify the corrosion processes involved during immersion of fuel cladding. In this project, state-of-the-art characterisation techniques were employed to image the corroding surfaces of two nuclear fuel cladding materials: stainless steel and Magnox. Advanced gas-cooled reactor fuel cladding consists of 20Cr-25Ni-Nb stabilised stainless steel and during irradiation the microstructure of the cladding undergoes significant changes, including grain boundary element depletion and segregation. High-speed atomic force microscopy with nanoscale resolution, enabled prec...
The corrosion patterns of 316L stainless steel is examined using a custom developed corrosion test c...
The current Canadian used nuclear fuel container (UFC) design uses a pressure‑grade carbon steel (CS...
The preparation of site-specific atom-probe tomography (APT) samples containing localized features h...
This thesis aims to investigate sites where corrosion initiates on an austenitic stainless steel use...
The role of niobium carbide (NbC) inclusions in directing the initiation of localised corrosion in s...
The UK radioactive waste inventory includes spent fuels from various reactor types, many of which ha...
Intermediate level nuclear waste (ILW) will be stored above ground in 304L stainless steel (SS) cont...
Due to radiation induced segregation (RIS) that occurs during fuel use in-reactor, portions of spent...
Niobium-stabilised austenitic stainless steel (20Cr-25Ni-Nb) has been immersed in sodium hydroxide, ...
Spent nuclear fuel (SNF) storage in reactor spent fuel pools (SFP) is one of the crucial stages of S...
The UK is currently transitioning from a closed nuclear fuel cycle to an open cycle. During this tra...
Researchers at the Materials Performance Centre in The University of Manchester School of Materials,...
In this research, mechanisms of end grain corrosion of 304L NAG tubes in boiling 9M HNO3-containing ...
AbstractThe corrosion of high level nuclear waste containers under permanent disposal conditions can...
The atmospheric corrosion of 304L and 3 16L austenitic stainless steels was investigated in conditio...
The corrosion patterns of 316L stainless steel is examined using a custom developed corrosion test c...
The current Canadian used nuclear fuel container (UFC) design uses a pressure‑grade carbon steel (CS...
The preparation of site-specific atom-probe tomography (APT) samples containing localized features h...
This thesis aims to investigate sites where corrosion initiates on an austenitic stainless steel use...
The role of niobium carbide (NbC) inclusions in directing the initiation of localised corrosion in s...
The UK radioactive waste inventory includes spent fuels from various reactor types, many of which ha...
Intermediate level nuclear waste (ILW) will be stored above ground in 304L stainless steel (SS) cont...
Due to radiation induced segregation (RIS) that occurs during fuel use in-reactor, portions of spent...
Niobium-stabilised austenitic stainless steel (20Cr-25Ni-Nb) has been immersed in sodium hydroxide, ...
Spent nuclear fuel (SNF) storage in reactor spent fuel pools (SFP) is one of the crucial stages of S...
The UK is currently transitioning from a closed nuclear fuel cycle to an open cycle. During this tra...
Researchers at the Materials Performance Centre in The University of Manchester School of Materials,...
In this research, mechanisms of end grain corrosion of 304L NAG tubes in boiling 9M HNO3-containing ...
AbstractThe corrosion of high level nuclear waste containers under permanent disposal conditions can...
The atmospheric corrosion of 304L and 3 16L austenitic stainless steels was investigated in conditio...
The corrosion patterns of 316L stainless steel is examined using a custom developed corrosion test c...
The current Canadian used nuclear fuel container (UFC) design uses a pressure‑grade carbon steel (CS...
The preparation of site-specific atom-probe tomography (APT) samples containing localized features h...