Radiation-induced segregation behavior in austenitic stainless steels: Fast reactor versus light water reactor irradiations

Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007

Volumn 3, Issue , 2007, Pages 1641-1657

  Edwards, Dan ^a   Simonen, Ed ^a   Bruemmer, Stephen ^a  

^a PACIFIC NORTHWEST NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

AUSTENITIC; DOSE-DEPENDENT; GRAIN-BOUNDARY COMPOSITION; HIGH-DOSE; HIGH-PURITY; IMPURITY ELEMENTS; INTERNATIONAL CONFERENCES; IRRADIATED MATERIALS; IRRADIATION ENVIRONMENTS; LIGHT WATER; NUCLEAR POWER SYSTEMS; NUCLEAR SOCIETY; RADIATION-INDUCED SEGREGATION; STAINLESS STEELS;

ALLOYING ELEMENTS; AUSTENITIC STAINLESS STEEL; AUSTENITIC STEEL; CRYSTAL GROWTH; DEGRADATION; ELECTRIC POWER SYSTEMS; ELECTRIC POWER TRANSMISSION NETWORKS; FAST REACTORS; GRAIN BOUNDARIES; INTERLOCKING SIGNALS; IRRADIATION; LIGHT WATER REACTORS; NUCLEAR ENERGY; NUCLEAR REACTORS; POWER TRANSMISSION; ROUGHNESS MEASUREMENT; SEGREGATION (METALLOGRAPHY); SILICON; STAINLESS STEEL; SULFATE MINERALS;

RADIATION;

EID: 52349093723     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

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