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ODS steel as structral material for high temperature nuclear reactors

Oxide dispersed strengthened (ODS) ferritic-martensitic steels are investigated as possible structural material for the future generation of High Temperature Gas Cooled Nuclear Reactors. The Ni based austenitic ODS superalloys are not considered, because of the Ni presence, which is unfavorable unde...

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Bibliographic Details
Published in:Вопросы атомной науки и техники
Date:2005
Main Authors: Pouchon, M.A., Dobeli, M., Schelldorfer, R., Chen, J., Hoffelner, W., Degueldre, C.
Format: Article
Language:English
Published: Національний науковий центр «Харківський фізико-технічний інститут» НАН України 2005
Subjects:
Материалы перспективных ядерных реакторов
Online Access:https://nasplib.isofts.kiev.ua/handle/123456789/80401
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Journal Title:Digital Library of Periodicals of National Academy of Sciences of Ukraine
Cite this:ODS steel as structral material for high temperature nuclear reactors / M.A. Pouchon, M. Dobeli, R. Schelldorfer, J. Chen, W. Hoffelner, C. Degueldre // Вопросы атомной науки и техники. — 2005. — № 3. — С. 122-127. — Бібліогр.: 9 назв. — англ.

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Digital Library of Periodicals of National Academy of Sciences of Ukraine

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