FFTF reload core nuclear design for increased experimental capability
In anticipation of continued growth in the FTR experimental irradiations program, the enrichments for the next batches of reload driver fuel to be manufactured have been increased to provide a substantially enlarged experimental reactivity allowance. The enrichments for these fuel assemblies, termed ''Cores 3 and 4,'' were selected to meet the following objectives and constraints: (1) maintain a reactor power capability of 400 MW (based on an evaluation of driver fuel centerline melting probability at 15 percent overpower); (2) provide a peak neutron flux of nominally 7 x 10/sup 15/ n/cm/sup 2/-sec, with a minimum acceptable value of 95 percent of this (i.e., 6.65 x 10/sup 15/ n/cm/sup 2/-sec); and (3) provide the maximum experimental reactivity allowance that is consistent with the above constraints.
- Research Organization:
- Hanford Engineering Development Lab., Richland, Wash. (USA)
- DOE Contract Number:
- E(45-1)-2170
- OSTI ID:
- 7339412
- Report Number(s):
- HEDL-SA-815; CONF-760622-50
- Country of Publication:
- United States
- Language:
- English
Similar Records
Central fuel worth in the Fast Test Reactor (FTR) engineering mockup
FFTF driver fuel experience
Related Subjects
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
DESIGN
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
FUEL ELEMENTS
LIQUID METAL COOLED REACTORS
REACTIVITY
REACTOR COMPONENTS
REACTOR CORES
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
SPECIFICATIONS
TEST REACTORS