Assessment of the corrosion behaviour of structural materials in the water coolant of ITER

Journal of Nuclear Materials

Volumn 258-263, Issue PART 1 A, 1998, Pages 351-356

  Belous, V ^a   Kalinin, G ^b   Lorenzetto, P ^b   Velikopolskiy, S ^a  

^a DOLLEZHAL RESEARCH AND DEVELOPMENT INSTITUTE OF POWER ENGINEERING NIKIET   (Russian Federation)

^b MAX PLANCK INSTITUT FÜR PLASMAPHYSIK   (Germany)

Author keywords

[No Author keywords available]

Indexed keywords

COPPER ALLOYS; COPPER CORROSION; EXPERIMENTAL REACTORS; HYDROGEN; HYDROGEN PEROXIDE; PH EFFECTS; RADIATION EFFECTS; STAINLESS STEEL; STEEL CORROSION; STRESS CORROSION CRACKING; THERMAL EFFECTS; WATER COOLED REACTORS;

FUSION REACTOR MATERIALS; INTERNATIONAL THERMONUCLEAR EXPERIMENTAL REACTOR (ITER); STAINLESS STEEL 316L(N)-IG;

TOKAMAK DEVICES;

EID: 0032182018     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0022-3115(98)00272-4     Document Type: Article

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