Fracture behavior of austenitic stainless steels irradiated in PWR

Journal of Nuclear Materials

Volumn 378, Issue 2, 2008, Pages 211-219

  Fukuya, K ^a   Nishioka, H ^a   Fujii, K ^a   Kamaya, M ^a   Miura, T ^a   Torimaru, T ^b  

^a INSTITUTE OF NUCLEAR SAFETY SYSTEM   (Japan)

^b NIPPON NUCLEAR FUEL DEVELOPMENT CO LTD   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

AUSTENITIC STAINLESS STEEL; AUSTENITIC STEEL; BRITTLE FRACTURE; CORROSION RESISTANT ALLOYS; DUCTILE FRACTURE; FRACTURE; FRACTURE FIXATION; FRACTURE TESTING; IMPACT TESTING; NUCLEAR REACTORS; PRESSURIZED WATER REACTORS; SMALL NUCLEAR REACTORS; STAINLESS STEEL; STEEL CORROSION; STEEL METALLURGY; TENSILE TESTING; TESTING;

(I ,J) CONDITIONS; ABSORBED ENERGY; AUSTENITIC; DEFORMATION MODES; ELSEVIER (CO); FRACTURE BEHAVIORS; HIGH STRAIN RATE (HSR); HIGH TEMPERATURE (HT); IMPACT TESTS; INTER-GRANULAR (IG) FRACTURE; LITERATURE DATA; MACROSCOPICALLY; PRESSURIZED WATER; SLOW-STRAIN-RATE (SSR); STRAIN RATE (IGC:D7); TEST TEMPERATURES; UNIAXIAL TENSILE TESTING;

STRAIN RATE;

EID: 48049101383     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.jnucmat.2008.06.028     Document Type: Article

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