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Validation of constraint-based methodology in structural integrity of ferritic steels for nuclear reactor pressure vessels

✍ Scribed by D. P. G. LIDBURY; A. H. SHERRY; B. R. BASS; P. GILLES; D. CONNORS; U. EISELE; E. KEIM; H. KEINANEN; K. WALLIN; D. LAUEROVA; S. MARIE; G. NAGEL; K. NILSSON; D. SIEGELE; Y. WADIER

Book ID
109015225
Publisher
John Wiley and Sons
Year
2006
Tongue
English
Weight
638 KB
Volume
29
Category
Article
ISSN
8756-758X

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Carbon redistribution between an austeni
Carbon redistribution between an austenitic cladding and a ferritic steel for pressure vessels of a nuclear reactor
✍ J. PavlovskΓ½; B. Million; K. CΓ­ha; K. StrΓ‘nskΓ½ πŸ“‚ Article πŸ“… 1991 πŸ› Elsevier Science 🌐 English βš– 697 KB

In this work, carbon redistribution between an austenitic cladding and a ferritic-carbidic steel for pressure vessels of the Voronez water energy nuclear reactor is studied. The carbon concentration in the surroundings of the weld interface was determined by electron beam microanalysis. The method o