Subchannel code for sodium boiling in LMFBR fuel bundles
Conference
·
OSTI ID:5564627
The CAPRICORN computer code is being developed with the US Fast Reactor Safety program to predict blockage formation and coalability in fuel pin bundles during core disruptive accidents. This code is an extension of the COBRA family of codes. An extension of the ICE solution procedure is used where the mass and energy conservation equations are solved implicitly for pressure and enthalpy in an inner iteration loop. The CAPRICORN code was used to analyze the final and most severe boiling transient of the W-1 SLSF experiment (an in-reactor simulation of a pipe rupture event). Comparison of the CAPRICORN analysis and experimental data was good enough to warrant further improvement and development of the code.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- AC06-76FF02170
- OSTI ID:
- 5564627
- Report Number(s):
- HEDL-SA-2965-S; CONF-831047-98; ON: DE84001681
- Country of Publication:
- United States
- Language:
- English
Similar Records
CAPRICORN subchannel code for sodium boiling in LMFBR fuel bundles. [Comparison with W-1 SLSF pipe rupture]
Two-dimensional computational modeling of sodium boiling in simulated LMFBR fuel-pin bundles
Simulations of loss-of-flow accidents in an LMFBR with the Sodium Loop Safety Facility
Conference
·
Sat Aug 13 00:00:00 EDT 1983
·
OSTI ID:5641755
Two-dimensional computational modeling of sodium boiling in simulated LMFBR fuel-pin bundles
Conference
·
Wed Dec 31 23:00:00 EST 1980
·
OSTI ID:6463741
Simulations of loss-of-flow accidents in an LMFBR with the Sodium Loop Safety Facility
Journal Article
·
Wed Feb 29 23:00:00 EST 1984
· Nucl. Saf.; (United States)
·
OSTI ID:6815784
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BOILING
BREEDER REACTORS
C CODES
COMPUTER CODES
EPITHERMAL REACTORS
FAILURES
FAST REACTORS
FBR TYPE REACTORS
FLOW BLOCKAGE
FUEL ASSEMBLIES
FUEL ELEMENTS
FUEL PINS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
PHASE TRANSFORMATIONS
PIPES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
SAFETY
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BOILING
BREEDER REACTORS
C CODES
COMPUTER CODES
EPITHERMAL REACTORS
FAILURES
FAST REACTORS
FBR TYPE REACTORS
FLOW BLOCKAGE
FUEL ASSEMBLIES
FUEL ELEMENTS
FUEL PINS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
PHASE TRANSFORMATIONS
PIPES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
SAFETY