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
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description 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 (
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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 (&lt;1 × 10 19 m −3) of radiation-enhanced precipitates was observed in the matrix. No cavities were observed. These features are correlated with the changes in tensile properties. It is concluded that the dislocation loops and the black dots cause irradiation hardening and a decrease in the uniform elongation in the 316LN steel irradiated at low temperatures.</description><identifier>ISSN: 0022-3115</identifier><identifier>EISSN: 1873-4820</identifier><identifier>DOI: 10.1016/S0022-3115(99)00009-4</identifier><identifier>CODEN: JNUMAM</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Applied sciences ; Controled nuclear fusion plants ; Energy ; Energy. 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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 (&lt;1 × 10 19 m −3) of radiation-enhanced precipitates was observed in the matrix. No cavities were observed. These features are correlated with the changes in tensile properties. It is concluded that the dislocation loops and the black dots cause irradiation hardening and a decrease in the uniform elongation in the 316LN steel irradiated at low temperatures.</description><subject>Applied sciences</subject><subject>Controled nuclear fusion plants</subject><subject>Energy</subject><subject>Energy. 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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 (&lt;1 × 10 19 m −3) of radiation-enhanced precipitates was observed in the matrix. No cavities were observed. These features are correlated with the changes in tensile properties. It is concluded that the dislocation loops and the black dots cause irradiation hardening and a decrease in the uniform elongation in the 316LN steel irradiated at low temperatures.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/S0022-3115(99)00009-4</doi><tpages>7</tpages></addata></record>
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subjects 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
title Relationship between hardening and damage structure in austenitic stainless steel 316LN irradiated at low temperature in the HFIR
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