Feedback components of a U20Pu10Zr-fueled compared to a U10Zr-fueled EBR-II
Conference
·
OSTI ID:10120261
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:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 10120261
- 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
·
Thu Dec 31 23:00:00 EST 1987
·
OSTI ID:5854980
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
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100
220400
CONTROL ELEMENTS
CONTROL SYSTEMS
E CODES
EBR-2 REACTOR
FEEDBACK
FUEL ELEMENTS
NUCLEAR FUELS
POWER REACTORS
BREEDING
REACTIVITY
REACTOR INTERNALS
REACTOR SAFETY
THEORY AND CALCULATION
THERMAL CONDUCTIVITY
210500
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100
220400
CONTROL ELEMENTS
CONTROL SYSTEMS
E CODES
EBR-2 REACTOR
FEEDBACK
FUEL ELEMENTS
NUCLEAR FUELS
POWER REACTORS
BREEDING
REACTIVITY
REACTOR INTERNALS
REACTOR SAFETY
THEORY AND CALCULATION
THERMAL CONDUCTIVITY