A REVIEW ON CURRENT STATUS OF ALLOYS 617 AND 230 FOR GEN IV NUCLEAR REACTOR INTERNALS AND HEAT EXCHANGERS
Journal Article
·
· Journal of Pressure Vessel Technology
- ORNL
Alloys 617 and 230 are currently identified as two leading candidate metallic materials in the down selection for applications at temperatures above 760 C in the Gen IV Nuclear Reactor Systems. Qualifying the materials requires significant information related to Codification, mechanical behavior modeling, metallurgical stability, environmental resistance, and many other aspects. In the present paper, material requirements for the Gen IV Nuclear Reactor Systems are discussed; certain available information regarding the two alloys under consideration for the intended applications are reviewed and analyzed. Suggestions are presented for further R&D activities for the materials selection.
- Research Organization:
- Oak Ridge National Laboratory (ORNL)
- Sponsoring Organization:
- NE USDOE - Office of Nuclear Energy
- DOE Contract Number:
- AC05-00OR22725
- OSTI ID:
- 964691
- Journal Information:
- Journal of Pressure Vessel Technology, Journal Name: Journal of Pressure Vessel Technology Journal Issue: 4 Vol. 131; ISSN JPVTAS; ISSN 0094-9930
- Country of Publication:
- United States
- Language:
- English
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