Relationship between hardening and damage structure in austenitic stainless steel 316LN irradiated at low temperature in the HFIR

An austenitic stainless steel 316LN irradiated to damage levels of about 3 dpa at irradiation temperatures of about 90°C and 250°C has been examined by transmission electron microscopy. The irradiation at 90°C and 250°C induced a dislocation loop density of 3.5 × 10 22 and 5.2 × 10 22 m −3, and a bl...

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Veröffentlicht in:	Journal of nuclear materials 1999-06, Vol.273 (1), p.95-101
Hauptverfasser:	Hashimoto, N, Wakai, E, Robertson, J.P
Format:	Artikel
Sprache:	eng
Schlagworte:	Applied sciences Controled nuclear fusion plants Energy Energy. Thermal use of fuels Exact sciences and technology Installations for energy generation and conversion: thermal and electrical energy
Online-Zugang:	Volltext
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Zusammenfassung:	An austenitic stainless steel 316LN irradiated to damage levels of about 3 dpa at irradiation temperatures of about 90°C and 250°C has been examined by transmission electron microscopy. The irradiation at 90°C and 250°C induced a dislocation loop density of 3.5 × 10 22 and 5.2 × 10 22 m −3, and a black dot density of 2.2 × 10 23 and 1.1 × 10 23 m −3, respectively, in the steel. A low density (
ISSN:	0022-3115 1873-4820
DOI:	10.1016/S0022-3115(99)00009-4