Mechanical and microstructural properties of a hipped RAFM ODS-steel

Lindau, R.; Möslang, A.; Schirra, M.; Schloßmacher, P.; Klimenkov, M.

doi:10.1016/s0022-3115(02)01045-0

Cited by 265 publications

(141 citation statements)

References 8 publications

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“…More recently, programs were begun in the fusion reactor programs in Japan, 132 Europe, 133 and the United States. 134,135 A primary objective of these programs, as in the programs before them, is to solve the problem of the 127 "bamboo-like grain structure and a strong deformation texture" which gives rise to anisotropic mechanical properties, especially an inferior biaxial creep-rupture strength.…”

Section: Ferritic and Martensitic Steels For The Futurementioning

confidence: 99%

Elevated temperature ferritic and martensitic steels and their application to future nuclear reactors

Klueh¹

2005

International Materials Reviews

474

176

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In the 1970s, high chromium (9-12%Cr) ferritic/martensitic steels became candidates for elevated temperature applications in the core of fast reactors. Steels developed for conventional power plants, such as Sandvik HT9, a nominally Fe-12Cr-1Mo-0 . 5W-0 . 5Ni-0 . 25V-0 . 2C steel (composition in wt-%), were considered in the USA, Europe and Japan. Now, a new generation of fission reactors is in the planning stage, and ferritic, bainitic and martensitic steels are again candidates for in-core and out-of-core applications. Since the 1970s, advances have been made in developing steels with 2-12%Cr for conventional power plants that are significant improvements over steels originally considered. The present study will review the development of the new steels to illustrate the advantages they offer for the new reactor concepts. Elevated temperature mechanical properties will be emphasised. Effects of alloying additions on long-time thermal exposure with and without stress (creep) will be examined. Information on neutron radiation effects will be discussed as it applies to ferritic and martensitic steels.

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Section: Ferritic and Martensitic Steels For The Futurementioning

confidence: 99%

Elevated temperature ferritic and martensitic steels and their application to future nuclear reactors

Klueh¹

2005

International Materials Reviews

474

176

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“…The upper operating temperature for conventional RAFM steels is established at 550 °C. It has been demonstrated that one way to in crease this temperature up to around 700 °C is to disperse homoge neously hard nanosized oxide particles, such as Y 2 O 3 , into the steel matrix [4]. Moreover, such nanoparticles could act as sinks for trapping of helium atoms and point defects, thus retarding radiation induced materials degradation [5].…”

Section: Introductionmentioning

confidence: 99%

Microstructural characterization of Y2O3 ODS–Fe–Cr model alloys

Castro

Muñóz

Monge

et al. 2009

Journal of Nuclear Materials

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Abstract:Two Fe 12 wt% Cr alloys, one containing 0.4 wt% Y 2 O 3 and the other Y 2 O 3 free, have been produced by mechanical alloying followed by hot isostatic pressing. These oxide dispersion strengthened and refer ence alloys were characterized both in the as HIPed state and after tempering by transmission electron microscopy and atom probe tomography. The as HIPed alloys exhibited the characteristic microstructure of lath martensite and contained a high density of dislocations. Small voids with sizes <10 nm were also observed. Both alloys also contained M 3 C and M 23 C 6 carbides (M Cr, Fe) probably as a result of C ingress during milling. After tempering at 1023 K for 4 h the microstructures had partially recovered. In the recovered regions, martensite laths were replaced by equiaxed grains in which M 23 C 6 carbides decorated the grain boundaries. In the ODS alloy nanoparticles containing Y were commonly observed within grains, although they were also present at grain boundaries and adjacent to large carbides.

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“…This drawback can be overcome by either using protection layers of silicon (Si), B, or by Mo-Si-B compounds. [2,3,4] In addition, the discussion includes oxide dispersion strengthened (ODS) steels (austenitic [5,6] , ferritic [7,8] and ferritic-martensitic [9] ), directionally solidified NiAl-X (Cr, Mo) eutectics [10,11,12,13] , Co-Re alloys [14,15] , and silicon carbide (SiC) [16,17] or carbonfiber-reinforced silicon carbide (C/SiC). Within the current discussion of the "beyond Ni-base super alloys", the authors want to include tungsten laminates as a new innovative material system.…”

Section: Introductionmentioning

confidence: 99%

Tungsten (W) Laminate Pipes for Innovative High Temperature Energy Conversion Systems

et al. 2014

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The aim of this paper is to present the mechanical properties of tungsten laminate pipes made of tungsten foil and to discuss their use in innovative high temperature energy conversion systems.Tungsten is the metal with the highest melting point of all metals and would therefore be an excellent fit for high temperature applications. But tungsten has one major drawback which is its low fracture toughness at room temperature (RT) or its high brittle-to-ductile transition 2 temperature (BDTT). However, one of the extraordinary properties of tungsten is that by cold working the BDTT can be shifted to lower temperatures. At the extreme, this results in a tungsten foil with a BDTT below -120°C combined with a RT fracture toughness of 70 MPa m 1/2 .By rolling up and joining a tungsten foil, tungsten laminate pipes can be synthesized that can dissipate at least 20 J in a Charpy impact test at RT and survive a burst test at RT at 1000 bar without any residual damage. The technical maturity of these W laminate pipes is approved by high heat flux tests performed at the Plataforma Solar de Almería, Spain, as well as at the

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Mechanical and microstructural properties of a hipped RAFM ODS-steel

Cited by 265 publications

References 8 publications

Elevated temperature ferritic and martensitic steels and their application to future nuclear reactors

Elevated temperature ferritic and martensitic steels and their application to future nuclear reactors

Microstructural characterization of Y2O3 ODS–Fe–Cr model alloys

Tungsten (W) Laminate Pipes for Innovative High Temperature Energy Conversion Systems

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