Fe-13 Cr-Ti-Mo ferritic alloy as material for a fast reactor

C. Gaspard; E. Diderrich; V. Leroy; J. J. Huet; L. Habraken

doi:10.1016/0022-3115(77)90222-7

Fe-13 Cr-Ti-Mo ferritic alloy as material for a fast reactor

C. Gaspard, E. Diderrich, V. Leroy, J. J. Huet, L. Habraken

Research output › peer-review

Abstract

Recent experimental work tends to indicate that embrittlement and swelling due to radiation by fast neutrons are not so important in ferritic as in austenitic stainless steels. For this reason, a Fe-13 Cr-Ti-Mo ferritic alloy has been developed as material for a fast reactor. This alloy is compatible with a sodium environment and derives its mechanical properties from solid-solution hardening and χ-phase precipitation. Mechanical properties have been investigated on this ferritic alloy in the cold rolled and annealed conditions. Stress rupture properties at 550°C have been compared with those of two commercial ferritic steels namely the X 20 Cr Mo (W) V and X 10 Cr 13 steels.

Original language	English
Pages (from-to)	104-110
Number of pages	7
Journal	Journal of Nuclear Materials
Volume	68
Issue number	1
DOIs	https://doi.org/10.1016/0022-3115(77)90222-7
State	Published - Sep 1977

ASJC Scopus subject areas

Nuclear and High Energy Physics
General Materials Science
Nuclear Energy and Engineering

Access to Document

10.1016/0022-3115(77)90222-7

Cite this

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title = "Fe-13 Cr-Ti-Mo ferritic alloy as material for a fast reactor",

abstract = "Recent experimental work tends to indicate that embrittlement and swelling due to radiation by fast neutrons are not so important in ferritic as in austenitic stainless steels. For this reason, a Fe-13 Cr-Ti-Mo ferritic alloy has been developed as material for a fast reactor. This alloy is compatible with a sodium environment and derives its mechanical properties from solid-solution hardening and χ-phase precipitation. Mechanical properties have been investigated on this ferritic alloy in the cold rolled and annealed conditions. Stress rupture properties at 550°C have been compared with those of two commercial ferritic steels namely the X 20 Cr Mo (W) V and X 10 Cr 13 steels.",

author = "C. Gaspard and E. Diderrich and V. Leroy and Huet, {J. J.} and L. Habraken",

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AU - Gaspard, C.

AU - Diderrich, E.

AU - Leroy, V.

AU - Huet, J. J.

AU - Habraken, L.

PY - 1977/9

Y1 - 1977/9

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AB - Recent experimental work tends to indicate that embrittlement and swelling due to radiation by fast neutrons are not so important in ferritic as in austenitic stainless steels. For this reason, a Fe-13 Cr-Ti-Mo ferritic alloy has been developed as material for a fast reactor. This alloy is compatible with a sodium environment and derives its mechanical properties from solid-solution hardening and χ-phase precipitation. Mechanical properties have been investigated on this ferritic alloy in the cold rolled and annealed conditions. Stress rupture properties at 550°C have been compared with those of two commercial ferritic steels namely the X 20 Cr Mo (W) V and X 10 Cr 13 steels.

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