Initial Physics Measurements on FFTF
- Hanford Engineering Development Lab., Richland, WA (United States)
Initial criticality of the Fast Flux Test Facility (FFTF) was achieved on February 9, 1980, at 3:45 p.m. During the period November 27, 1979, to March 8, 1980, fuel was loaded into the FFTF core, initial criticality was achieved, and several subcritical physics measurements were performed. The data obtained from initial FFTF nuclear operation are presented. Specifically, the absolute and relative neutron count rates were predicted for the bulk of the seventy-three fuel loadings of FFTF. Agreement between predicted and observed values is illustrated. Severe variations of fission chamber detection efficiency in the reactor shield is contrasted with that near the core center. Control rod worths, measured by the rod drop inverse kinetics method, are compared with predictions based upon Engineering Mockup Critical (EMC) evaluations. Control rod reactivity worth curves measured by rod run-in inverse kinetics are given.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC14-76FF02170
- OSTI ID:
- 5317679
- Report Number(s):
- HEDL-SA--2163; CONF-800607--68
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
CONTROL ROD WORTHS
Control Rod
DATA
DATA COMPILATION
EPITHERMAL REACTORS
Engineering Mockup Critical (EMC) Evaluations
FAST REACTORS
FFTF REACTOR
Fast Flux Test Facility (FFTF)
INFORMATION
KINETICS
LIQUID METAL COOLED REACTORS
NEUTRON FLUX
NUMERICAL DATA
Nuclear Criticality Safety Program (NCSP)
RADIATION FLUX
REACTIVITY WORTHS
REACTOR KINETICS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
TEST REACTORS