Initial Physics Measurements on FFTF
- Hanford Engineering Development Laboratories, 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 are 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 Laboratories, Richland, WA (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- OSTI ID:
- 6596426
- Report Number(s):
- CONF-800607-
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 34; ISSN TANSA; ISSN 0003-018X
- Publisher:
- American Nuclear Society
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
CRITICALITY
EPITHERMAL REACTORS
Engineering Mockup Critical (EMC) Evaluations
FAST REACTORS
FFTF Core
FFTF REACTOR
Fast Flux Test Facility (FFTF)
Fuel
KINETICS
LIQUID METAL COOLED REACTORS
Nuclear Criticality Safety Program (NCSP)
REACTIVITY WORTHS
REACTOR COMPONENTS
REACTOR CORES
REACTOR KINETICS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
TEST REACTORS