Fast flux test facility radioisotope production and medical applications
Creators
- 1. Battelle-Pacific Northwest National Lab., Richland, WA (United States)
Description
The Fast Flux Test Facility (FFTF) is a 400-MW, sodium-cooled reactor that operated successfully from 1982 to 1992, conducting work in support of the liquid-metal reactor industry by developing and testing fuel assemblies, control rods, and other core reactor components. Upon termination of this program, the primary mission of FFTF ended, and it was placed in a standby mode in 1993. However, in January 1997 the U.S. Secretary of Energy requested that FFTF be evaluated for a future mission that would consist of a primary goal of producing tritium for nuclear defense applications and a secondary goal of supplying medical isotopes for research and clinical applications. Production by FFTF of tritium for U.S. nuclear weapons would augment the dual-track strategy now under consideration for providing a long-term tritium supply in the United States (consisting of a light water reactor option and an accelerator option). A decision by the Secretary of Energy on proceeding with steps leading toward the possible reactivation of FFTF will be made before the end of 1998
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 77
- Journal Page Range
- p. 541.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- 1997 American Nuclear Society (ANS) winter meeting.
- Dates
- 16-20 Nov 1997.
- Place
- Albuquerque, NM (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 29021224
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FFTF REACTOR; FUEL ASSEMBLIES; ISOTOPE PRODUCTION; NUCLEAR MEDICINE; REACTOR COMPONENTS
- Descriptors DEC
- EPITHERMAL REACTORS; FAST REACTORS; LIQUID METAL COOLED REACTORS; MEDICINE; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SODIUM COOLED REACTORS; TEST FACILITIES; TEST REACTORS
Optional Information
- Secondary number(s)
- CONF-971125--.