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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| Published in: | Вопросы атомной науки и техники |
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| Date: | 2005 |
| Main Authors: | , , , , , |
| Format: | Article |
| Language: | English |
| Published: |
Національний науковий центр «Харківський фізико-технічний інститут» НАН України
2005
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| Subjects: | |
| 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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