Development of a Controlled Material Specification for Alloy 617 for Nuclear Applications [electronic resource].
- Published:
- Washington, D.C. : United States. Office of the Assistant Secretary for Nuclear Energy, 2005.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy - Additional Creators:
- Oak Ridge National Laboratory, United States. Office of the Assistant Secretary for Nuclear Energy, and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access:
- Free-to-read Unrestricted online access
- Summary:
- 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.
- Report Numbers:
- E 1.99:ornl/tm-2005/504
ornl/tm-2005/504 - Subject(s):
- Other Subject(s):
- Note:
- Published through SciTech Connect.
05/01/2005.
"ornl/tm-2005/504"
"AF3620100"
"NEAF265"
Ren, Weiju [ORNL]. - Funding Information:
- DE-AC05-00OR22725
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