Development of New Heats of Advanced Ferritic/Martensitic Alloys [electronic resource].
- Published
- Washington, D.C. : United States. Office of the Assistant Secretary for Nuclear Energy, 2017.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy - Physical Description
- 9 pages : digital, PDF file
- Additional Creators
- Los Alamos 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
- The Fuel Cycle Research and Development program is investigating methods of transmuting minor actinides in various fuel cycle options. To achieve this goal, new fuels and cladding materials must be developed and tested to high burnup levels (e.g. >20%) requiring cladding to withstand very high doses (greater than 200 dpa) while in contact with the coolant and the fuel. To develop and qualify materials to a total fluence greater than 200 dpa requires development of advanced alloys and irradiations in fast reactors to test these alloys. Recent results from testing numerous ferritic/martensitic steels at low temperatures suggest that improvements in low temperature radiation tolerance can be achieved through carefully controlling the nitrogen content in these alloys. Thus, four new heats of HT-9 were produced with controlled nitrogen content: two by Metalwerks and two by Sophisticated Alloys. Initial results on these new alloys are presented including microstructural analysis and hardness testing. Future testing will include irradiation testing with ions and in reactor.
- Report Numbers
- E 1.99:la--ur-16-22051
la--ur-16-22051 - Subject(s)
- Note
- Published through SciTech Connect.
06/23/2017.
"la--ur-16-22051"
Stuart Andrew Maloy; Kimberly Shay Pestovich; Osman Anderoglu; Eda Aydogan. - Funding Information
- AC52-06NA25396
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