Feedback components of a U20Pu10Zr-fueled compared to a U10Zr-fueled EBR-II
Conference
·
OSTI ID:5854980
Calculated feedback components of the regional contributions of the power reactivity decrements (PRDs) and of the temperature coefficients of reactivity of a U20Pu10Zr-fueled and of a U10Zr-fueled Experimental Breeder Reactor II (EBR-II) are compared. The PRD components are also separated into power-to-flow dependent and solely power dependent parts. The effects of these values upon quantities useful for indicating the comparative potential inherent safety characteristics of these EBR-II loadings are presented.
- Research Organization:
- Argonne National Lab., IL (United States)
- Sponsoring Organization:
- DOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5854980
- Report Number(s):
- ANL/CP-73272; CONF-920308--10; ON: DE92007375
- Country of Publication:
- United States
- Language:
- English
Similar Records
Feedback components of a U20Pu10Zr-fueled compared to a U10Zr-fueled EBR-II
PRD (power-reactivity-decrement) components of a homogeneous U10Zr-fueled 900 MWt LMR
Delineations of power and power-to-flow feedback components of EBR-II
Conference
·
Fri Dec 30 23:00:00 EST 1988
·
OSTI ID:10120261
PRD (power-reactivity-decrement) components of a homogeneous U10Zr-fueled 900 MWt LMR
Conference
·
Thu Dec 31 23:00:00 EST 1987
·
OSTI ID:5123046
Delineations of power and power-to-flow feedback components of EBR-II
Conference
·
Tue Dec 31 23:00:00 EST 1985
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6891674
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100 -- Nuclear Reactor Technology-- Theory & Calculation
220400* -- Nuclear Reactor Technology-- Control Systems
BREEDER REACTORS
COMPUTER CODES
CONTROL ELEMENTS
E CODES
EBR-2 REACTOR
ENERGY SOURCES
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FEEDBACK
FUEL ELEMENTS
FUELS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
NUCLEAR FUELS
PHYSICAL PROPERTIES
POWER REACTORS
REACTIVITY
REACTOR COMPONENTS
REACTOR INTERNALS
REACTOR MATERIALS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SODIUM COOLED REACTORS
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100 -- Nuclear Reactor Technology-- Theory & Calculation
220400* -- Nuclear Reactor Technology-- Control Systems
BREEDER REACTORS
COMPUTER CODES
CONTROL ELEMENTS
E CODES
EBR-2 REACTOR
ENERGY SOURCES
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FEEDBACK
FUEL ELEMENTS
FUELS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
NUCLEAR FUELS
PHYSICAL PROPERTIES
POWER REACTORS
REACTIVITY
REACTOR COMPONENTS
REACTOR INTERNALS
REACTOR MATERIALS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SODIUM COOLED REACTORS
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES