FFTF reactor characterization program
Preparations are under way for the initial startup and testing of the Fast Flux Test Facility (FFTF). The FFTF Reactor Characterization Program is that part of the startup test plan that deals with the determination of the neutron, gamma ray and thermal hydraulic characteristics of the reactor. This program encompasses measurements and calculations of: neutron spectra, flux and fluence; gamma-ray spectra, dose and heating; fission rate distributions; capture rate distributions; other reaction rates of interest; fission product yields; and thermal hydraulic data. Measurements of these parameters will be made in the reactor core and reflectors, will extend vertically downward to the vicinity of the core support structure and upward to the top of the sodium pool, and will extend radially outward to include in-vessel fuel storage locations and the cavity between the reactor vessel and the concrete wall.
- Research Organization:
- Hanford Engineering Development Lab., Richland, Wash. (USA)
- DOE Contract Number:
- EY-76-C-14-2170
- OSTI ID:
- 5157752
- Report Number(s):
- HEDL-SA-1351; CONF-771036-10
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
KINETICS
LIQUID METAL COOLED REACTORS
MECHANICS
NEUTRON FLUX
NEUTRON SPECTRA
RADIATION FLUX
REACTOR KINETICS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
SPECTRA
TEST REACTORS