Published 1993
| Version v1
Journal article
The D9-4 experiment: Improving on the fast flux test facility driver pin
Description
The driver fuel system for the fast Flux Test Facility (FFTF) has proven to be a very robust and reliable spectrum liquid-metal reactor. A series of fuel assembly tests, has now been completed that incorporate unique improvements to extend the lifetime of the driver fuel design to increase the ease of fabrication, and to increase the breeding potential. The D9-4 test was a high-exposure fuel assembly in this series, and detailed examinations of this test have been completed. Commonalities with the standard FFTF driver fuel included dimensions and the use of uranium/plutonium mixed-oxide pellet fuel
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 68
- Journal Page Range
- p. 96-97.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- American Nuclear Society (ANS) annual meeting.
- Dates
- 20-24 Jun 1993.
- Place
- San Diego, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25022823
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BREEDING; DESIGN; FABRICATION; FFTF REACTOR; FUEL ELEMENTS; FUEL PELLETS; LIFETIME; MIXED OXIDE FUELS; PLUTONIUM OXIDES; TESTING; URANIUM OXIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; ENERGY SOURCES; EPITHERMAL REACTORS; FAST REACTORS; FUELS; LIQUID METAL COOLED REACTORS; MATERIALS; NUCLEAR FUEL CONVERSION; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SODIUM COOLED REACTORS; SOLID FUELS; TEST FACILITIES; TEST REACTORS; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS
Optional Information
- Secondary number(s)
- CONF-930601--.