Considerations of Alloy 617 Application in the Gen IV Nuclear Reactor Systems - Part II: Metallurgical Property Challenges
Conference
·
OSTI ID:964705
- ORNL
Alloy 617 is currently considered as a leading candidate material for high temperature components in the Gen IV Nuclear Reactor Systems. Because of the unprecedented severe working conditions beyond its commercial service experience required by the Gen IV systems, the alloy faces various challenges in both mechanical and metallurgical properties. Following a previous paper discussing the mechanical property challenges, this paper is focused on the challenges and issues in metallurgical properties of the alloy for the intended nuclear application. Considerations are given in details about its metallurgical stability and aging evolution, aging effects on mechanical properties, potential Co hazard, and internal oxidation. Some research and development activities are suggested with discussions on viability to satisfy the Gen IV Nuclear Reactor System needs.
- Research Organization:
- Oak Ridge National Laboratory (ORNL)
- Sponsoring Organization:
- NE USDOE - Office of Nuclear Energy
- DOE Contract Number:
- AC05-00OR22725
- OSTI ID:
- 964705
- Country of Publication:
- United States
- Language:
- English
Similar Records
Considerations of Alloy 617 Application in the Gen IV Nuclear Reactor Systems - Part I: Mechanical Property Challenges
A REVIEW ON CURRENT STATUS OF ALLOYS 617 AND 230 FOR GEN IV NUCLEAR REACTOR INTERNALS AND HEAT EXCHANGERS
A REVIEW OF AGING EFFECTS IN ALLOY 617 FOR GEN IV NUCLEAR REACTOR APPLICATIONS
Conference
·
Thu Dec 31 23:00:00 EST 2009
·
OSTI ID:964700
A REVIEW ON CURRENT STATUS OF ALLOYS 617 AND 230 FOR GEN IV NUCLEAR REACTOR INTERNALS AND HEAT EXCHANGERS
Journal Article
·
Wed Dec 31 23:00:00 EST 2008
· Journal of Pressure Vessel Technology
·
OSTI ID:964691
A REVIEW OF AGING EFFECTS IN ALLOY 617 FOR GEN IV NUCLEAR REACTOR APPLICATIONS
Conference
·
Sat Dec 31 23:00:00 EST 2005
·
OSTI ID:1093003