Under the microscope: Reduced activation ferritic martensitic steel Eurofer-97 following ion-Irradiation and high-temperature high-pressure water exposure

Clark, Ronald N.; Kumar, David; Hawes, Jonathan; Hughes, Liam; Zimina, Mariia; Burrows, Robert; Eloi, Jean-Charles; Hargreaves, James; Mo, Kun; Liu, Dong; ParkerQuaife, Elizabeth H.; Martin, Tomas

doi:10.1016/j.jnucmat.2024.155527

Under the microscope: Reduced activation ferritic martensitic steel Eurofer-97 following ion-Irradiation and high-temperature high-pressure water exposure

Journal Article · Sat Nov 16 23:00:00 EST 2024 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2024.155527· OSTI ID:2574124

Clark, Ronald N. ^[1]; Kumar, David ^[1]; ^[2]; ^[3]; ^[4]; Burrows, Robert ^[1]; Eloi, Jean-Charles ^[4]; ^[4]; ^[5]; Liu, Dong ^[4]; ParkerQuaife, Elizabeth H. ^[6]; ^[4]

National Nuclear Laboratory, Stonehouse (United Kingdom)
Culham Science Centre, Abingdon (United Kingdom). National Nuclear Laboratory
Univ. of Birmingham (United Kingdom)
Univ. of Bristol (United Kingdom)
Argonne National Laboratory (ANL), Argonne, IL (United States)
Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Here, 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.

View Accepted Manuscript (DOE)

Research Organization:: Argonne National Laboratory (ANL), Argonne, IL (United States)

Sponsoring Organization:: USDOE; European Union (EU); Engineering and Physical Sciences Research Council (EPSRC)

Grant/Contract Number:: AC02-06CH11357

OSTI ID:: 2574124

Alternate ID(s):: OSTI ID: 2479003

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 605; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Under the microscope: Reduced activation ferritic martensitic steel Eurofer-97 following ion-Irradiation and high-temperature high-pressure water exposure

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