Irradiation-Assisted Stress Corrosion Cracking of Austenitic Stainless Steels and Alloy 690 from Halden Phase-II Irradiations

Chen, Y.¹  Chopra, O. K.¹  Soppet, W. K.¹  Dietz Rago, Nancy L.² 

[1] Argonne National Lab. (ANL), Argonne, IL (United States);Argonne National

关键词: CRACKS;    STAINLESS STEEL-304;    STAINLESS STEEL-304L;    STAINLESS STEEL-316;    STAINLESS STEEL-316L;    INCONEL 690;    STRESS CORROSION;    WATER MODERATED REACTORS;    REACTOR INTERNALS;    IRRADIATION;    WATER COOLED REACTORS;    RADIATION DOSES;    NEUTRONS;    TEMPERATURE RANGE 0400-1000 K;    DUCTILITY;    RADIATION HARDENING;    METALLURGICAL EFFECTS;    EMBRITTLEMENT;   

DOI  :  10.2172/1224948
RP-ID  :  NUREG/CR--6965
PID  :  OSTI ID: 1224948
Others  :  Other: 118693
Others  :  TRN: US1500892

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来源: SciTech Connect

【 摘 要 】

This work is an ongoing effort at Argonne National Laboratory on the mechanistic study of irradiation-assisted stress corrosion cracking (IASCC) in the core internals of light water reactors.