Author： Vatulin A. Tselishchev A.
Publisher： Springer Publishing Company
ISSN： 0026-0673
Source： Metal Science and Heat Treatment, Vol.46, Iss.11-12, 2004-11, pp. : 463-468
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Abstract
The directions of development of stainless steels for fuel rod claddings and fuel element cans of fast neutron reactors are considered. The principles of complex alloying and treatment of steels ensuring low swelling at irradiation dozses of 80–90 dpa (dislocations per atom) are described. Ways for further development of functional characteristics of steels of austenitic and martensitic classes are outlined.
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