TY - JOUR
T1 - Under the microscope
T2 - Reduced Activation Ferritic Martensitic Steel Eurofer-97 Following Ion‑Irradiation and High‑Temperature High‑Pressure Water Exposure
AU - Clark, Ronald
AU - Kumar, David
AU - Hawes, Jonathan
AU - Hughes, Liam
AU - Zimina, Mariia
AU - Burrows, Robert W
AU - Eloi, Jean-Charles
AU - Hargreaves, James P
AU - Mo, Kun
AU - Liu, Dong
AU - Parker-Quaife, Elizabeth
AU - Martin, Tomas L
N1 - Publisher Copyright:
© 2024
PY - 2025/2/1
Y1 - 2025/2/1
N2 - This study is designed to characterise the microstructural behaviour of Eurofer-97 steel under ion irradiation and subsequent exposure to high-temperature high-pressure (HTHP) water. Eurofer-97, a ferritic-martensitic steel, has been developed to withstand the conditions of fusion reactors in the locations in contact with coolant with an elevated level of neutron flux, such as the breeder-wall blanket. The material has been studied after self-ion irradiation (using Fe ions) simulating the microstructural effects of neutron irradiation limited to the subsurface layer. The corrosion properties of the Eurofer-97 steel were studied by exposure to HTHP water up to 331°C. Advanced microstructural characterisation using scanning, transmission electron and focused ion beam microscopy was performed on the as-received microstructure and after ion irradiation. This was then characterised after exposure for 240 h in high-temperature water. Eurofer-97 had a dense, columnar Cr-rich inner oxide, followed by a Fe-rich outer oxide layer. In the irradiated condition the grain structure and oxide itself was less ordered. No appreciable difference in oxide thickness was identified between the irradiated and unirradiated specimens after this short exposure time.
AB - This study is designed to characterise the microstructural behaviour of Eurofer-97 steel under ion irradiation and subsequent exposure to high-temperature high-pressure (HTHP) water. Eurofer-97, a ferritic-martensitic steel, has been developed to withstand the conditions of fusion reactors in the locations in contact with coolant with an elevated level of neutron flux, such as the breeder-wall blanket. The material has been studied after self-ion irradiation (using Fe ions) simulating the microstructural effects of neutron irradiation limited to the subsurface layer. The corrosion properties of the Eurofer-97 steel were studied by exposure to HTHP water up to 331°C. Advanced microstructural characterisation using scanning, transmission electron and focused ion beam microscopy was performed on the as-received microstructure and after ion irradiation. This was then characterised after exposure for 240 h in high-temperature water. Eurofer-97 had a dense, columnar Cr-rich inner oxide, followed by a Fe-rich outer oxide layer. In the irradiated condition the grain structure and oxide itself was less ordered. No appreciable difference in oxide thickness was identified between the irradiated and unirradiated specimens after this short exposure time.
U2 - 10.1016/j.jnucmat.2024.155527
DO - 10.1016/j.jnucmat.2024.155527
M3 - Article (Academic Journal)
SN - 0022-3115
VL - 605
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
M1 - 155527
ER -