Development of very high-density low-enriched uranium fuels

Conference · Sat Feb 01 04:00:00 UTC 1997

OSTI ID:459691

Snelgrove, J L; Hofman, G L; Trybus, C L; Wiencek, T C

The RERTR program has recently begun an aggressive effort to develop dispersion fuels for research and test reactors with uranium densities of 8 to 9 g U/cm{sup 3}, based on the use of {gamma}-stabilized uranium alloys. Fabrication development teams and facilities are being put into place and preparations for the first irradiation test are in progress. The first screening irradiations are expected to begin in late April 1997 and first results should be available by end of 1997. Discussions with potential international partners in fabrication development and irradiation testing have begun.

• Research Organization: Argonne National Lab., IL (United States)
• Sponsoring Organization: USDOE Assistant Secretary for Human Resources and Administration, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 459691
• Report Number(s): ANL/TD/CP--91700; CONF-970228--2; ON: DE97003225
• Country of Publication: United States
• Language: English

Related Subjects

05 NUCLEAR FUELS
22 GENERAL STUDIES OF NUCLEAR REACTORS
DISPERSION NUCLEAR FUELS
EXPERIMENT PLANNING
RESEARCH AND TEST REACTORS
RESEARCH PROGRAMS
SLIGHTLY ENRICHED URANIUM