Development of a Controlled Material Specification for Alloy 617 for Nuclear Applications
- 1. Oak Ridge National Laboratory, TN (United States)
Description
Investigation is conducted in an effort to refine the standard specifications of Alloy 617 for the Very High Temperature Reactor applications. Background, motivation and rationale of the investigation are discussed. Historical data generated from various heats of the alloy are collected, sorted, and analyzed. The analyses include examination of mechanical property data and corresponding heat chemical composition, discussion on previous Alloy 617 specification development effort at the Oak Ridge National Laboratory, and assessment of the strengthening elements and mechanisms of the alloy. Based on the analyses, literature review, and knowledge of Ni base alloys, a tentative refined specification is recommended. Future work for verifying and improving the tentative refined specification is also suggested.
Availability note (English)
Available from http://info.ornl.gov/sites/publications/files/Pub92.pdf; PURL: https://www.osti.gov/servlets/purl/1034357/Additional details
Identifiers
Publishing Information
- Imprint Pagination
- vp.
- Report number
- ORNL/TM--2005/504
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 43048928
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- ALLOYS; CHEMICAL COMPOSITION; INCONEL 617; MECHANICAL PROPERTIES; NICKEL BASE ALLOYS; SPECIFICATIONS; VHTR REACTOR
- Descriptors DEC
- ALLOY-NI54CR22CO13MO9; ALLOYS; ALUMINIUM ADDITIONS; ALUMINIUM ALLOYS; CHROMIUM ALLOYS; COBALT ALLOYS; CORROSION RESISTANT ALLOYS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; INCONEL ALLOYS; MATERIALS; MOLYBDENUM ALLOYS; NICKEL ALLOYS; NICKEL BASE ALLOYS; POWER REACTORS; REACTORS; RESEARCH AND TEST REACTORS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS
Optional Information
- Contract/Grant/Project number
- AF3620100; NEAF265; AC05-00OR22725
- Notes
- doi 10.2172/1034357
- Funding organization
- NE USDOE - Office of Nuclear Energy (United States)