Review of methods for analysis of neutron streaming in the Fast Flux Test Facility reactor design
Conference
·
OSTI ID:7274456
The FFTF neutron streaming calculation is considered as consisting of four steps: (1) calculation of the source entering the reactor cavity, (2) calculation of the reactor cavity, (3) calculation of the reactor cavity shield, and (4) calculation of the vessel support system, head, and maintenance floor shield. Calculational methods used in each step are discussed. (DG)
- Research Organization:
- Oak Ridge National Lab., Tenn. (USA)
- OSTI ID:
- 7274456
- Report Number(s):
- CONF-760622-20
- 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
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
LIQUID METAL COOLED REACTORS
NEUTRON FLUX
RADIATION FLUX
RADIATION STREAMING
REACTOR COMPONENTS
REACTOR CORES
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SHIELDS
SODIUM COOLED REACTORS
TEST REACTORS
TWO-DIMENSIONAL CALCULATIONS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
LIQUID METAL COOLED REACTORS
NEUTRON FLUX
RADIATION FLUX
RADIATION STREAMING
REACTOR COMPONENTS
REACTOR CORES
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SHIELDS
SODIUM COOLED REACTORS
TEST REACTORS
TWO-DIMENSIONAL CALCULATIONS