Material science and manufacturing of heat-resistant reduced-activation ferritic–martensitic steels for fusion

Structural materials for fusion power reactors—the RF R&D activities

“…The steel properties and the mechanisms of phase-structural transformations in the steel at different technological stages of thermal treatment (TT) of articles are under investigation [7][8][9]12]. Some properties of the steel RUSFER-EK-181 are presented in figures 1-7.…”

“…The final choice of DEMO concepts (and therefore the choice of the structural material or vice versa the R&D level of the structural materials will determine the concept of the fusion power reactor) will be made, with high probability, on the basis of the results of the DEMO-test blanket programmes for ITER (2015-2020) and the high dose results for structural materials in the fast breeder reactors (FBRs, BN-600 [4], BN-800 [5], others) and neutron source IFMIF [6]. The RF structural materials R&D programme is a part of the RF programmes (materials parts) of controlled fusion power (1990)(1991)(1992)(1993)(1994)(1995)(1996)(1997)(1998)(1999)(2000)(2001)(2002)(2003)(2004)(2005)(2006)(2007)2008-2015-under preparation) [1][2][3] and the FBR programmes [2][3][7][8][9][10][11][12][13][14]. As the requirements of structural core materials and conditions of their exploitation in fusion reactors and FBRs are very similar, the RF FBRs (BOR-60, BN-350, BN-600) experience for materials science is important for the development of advanced steels and alloys for fusion applications.…”

Effect of self-ion irradiation on the microstructural changes of alloy EK-181 in annealed and severely deformed conditions

“…In-core structural materials for next-generation nuclear reactors require good radiation resistance to embrittlement and void swelling, but also require a rapid reduction of neutroninduced activity to meet low-activation goals [1][2][3][4]. Among various high-chromium reducedactivation ferritic/martensitic (F/M) alloys [1,5,6], the Russian alloy EK-181, often designated as "Rusfer", has been intensively studied as one promising candidate for in-core components for both fast reactors and fusion reactors [7].…”

Cracking of Martensitic Alloy EP-823 Under Controlled Potential

“…This alloy was developed by the Russians for nuclear applications because of its superior corrosion resistance resulting from the presence of increased silicon (Si) content. In addition, this alloy possesses significant resistance to swelling during high neutron exposure at temperatures up to 420°C, low rate of irradiation creep, and rather low activation compared to that of the austenitic stainless steels ( Ref 3,4). This alloy has also been reported to retain its high strength and ductility at elevated temperatures in irradiated conditions ( Ref 5).…”