Reactivity feedback and step response test in the experimental fast reactor JOYO
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5568179
- Research Organization:
- Power Reactor and Nuclear Fuel Development Corporation, 4002 Narita-cho, O-Arai-Machi, Higashi-Ibaraki Higashi-Ibaraki-Gun, Ibaraki-Ken
- OSTI ID:
- 5568179
- Report Number(s):
- CONF-830609-
- Journal Information:
- Trans. Am. Nucl. Soc.; (United States), Vol. 44; Conference: ANS annual meeting, Detroit, MI, USA, 12 Jun 1983
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
JOYO REACTOR
REACTOR KINETICS
BURNUP
COMPUTERIZED SIMULATION
COOLANTS
FEEDBACK
FUEL PELLETS
NEUTRON FLUX
NUCLEAR CORES
NUCLEAR FUELS
NUCLEAR MODELS
POWER COEFFICIENT
POWER RANGE 10-100 MW
REACTIVITY
REACTOR OPERATION
REACTOR SAFETY EXPERIMENTS
RESPONSE FUNCTIONS
ROD DROP METHOD
TEMPERATURE COEFFICIENT
BREEDER REACTORS
ENERGY SOURCES
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUELS
FUNCTIONS
KINETICS
LIQUID METAL COOLED REACTORS
MATERIALS
MATHEMATICAL MODELS
OPERATION
PELLETS
POWER REACTORS
RADIATION FLUX
REACTIVITY COEFFICIENTS
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
SIMULATION
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors
220900 - Nuclear Reactor Technology- Reactor Safety
22 GENERAL STUDIES OF NUCLEAR REACTORS
JOYO REACTOR
REACTOR KINETICS
BURNUP
COMPUTERIZED SIMULATION
COOLANTS
FEEDBACK
FUEL PELLETS
NEUTRON FLUX
NUCLEAR CORES
NUCLEAR FUELS
NUCLEAR MODELS
POWER COEFFICIENT
POWER RANGE 10-100 MW
REACTIVITY
REACTOR OPERATION
REACTOR SAFETY EXPERIMENTS
RESPONSE FUNCTIONS
ROD DROP METHOD
TEMPERATURE COEFFICIENT
BREEDER REACTORS
ENERGY SOURCES
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUELS
FUNCTIONS
KINETICS
LIQUID METAL COOLED REACTORS
MATERIALS
MATHEMATICAL MODELS
OPERATION
PELLETS
POWER REACTORS
RADIATION FLUX
REACTIVITY COEFFICIENTS
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
SIMULATION
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors
220900 - Nuclear Reactor Technology- Reactor Safety