Oxidation of advanced zirconium cladding alloys in steam at temperatures in the range of 600-1200 °c

Oxidation of Metals

Volumn 76, Issue 3-4, 2011, Pages 215-232

  Steinbrück, Martin ^a   Vér, Nóra ^b   Groe, Mirco ^a  

^a KARLSRUHE INSTITUTE OF TECHNOLOGY   (Germany)

^b AEKI   (Hungary)

Author keywords

Cladding; High temperature oxidation; Light water reactor; Nuclear safety; Zirconium alloys

Indexed keywords

A-THERMAL; BEYOND DESIGN BASIS ACCIDENT; BURN UP; CLADDING ALLOYS; LIGHT WATER; NUCLEAR SAFETY; OPERATIONAL CONDITIONS; OXIDATION KINETICS; OXIDATION RATES; OXIDE SCALE; POST-TEST ANALYSIS; REFERENCE MATERIAL; STRONG CORRELATION; TEMPERATURE RANGE; TRANSIENT TESTS; WESTINGHOUSE; ZIRCALOY-4;

CLADDING (COATING); DESIGN; HYDROGEN; INVESTMENTS; LIGHT WATER REACTORS; NEUTRON RADIOGRAPHY; OXIDATION; PRESSURIZED WATER REACTORS; RADIOLOGY; SCALE (DEPOSITS); ZIRCONIUM; ZIRCONIUM ALLOYS; ZIRCONIUM COMPOUNDS;

ALLOYS;

EID: 80052701451     PISSN: 0030770X     EISSN: None     Source Type: Journal    
DOI: 10.1007/s11085-011-9249-3     Document Type: Article

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