CAMEL II 37-pin/7-pin intra-pin fuel injection test
Conference
·
OSTI ID:6837072
It is concluded that the 2-D effects of this test allowed the coolant to bypass the injected fuel, prohibiting any significant intermixing of the fuel and sodium to take place. This lack of intermixing resulted in a benign pressurization event and significantly reduced the fuel sweepout over previous CAMEL tests. The resulting fuel blockage is predicted to be in a coolable state when analyzed with PLUGCO, a numerical computer code for analysis of post-transient blockage coolability.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6837072
- Report Number(s):
- CONF-840614-29; ON: DE84006326
- Country of Publication:
- United States
- Language:
- English
Similar Records
Dispersal of molten uranium alloy fuel under simulated transient overpower accident conditions: The CAMEL II C9 test
Fuel pins and core response under liquid-metal fast breeder reactor transient overpower accident conditions
CAMEL II 37-pin/7-pin intra-pin fuel injection test
Technical Report
·
Fri May 01 00:00:00 EDT 1987
·
OSTI ID:713600
Fuel pins and core response under liquid-metal fast breeder reactor transient overpower accident conditions
Journal Article
·
Fri Nov 30 23:00:00 EST 1979
· Nucl. Technol.; (United States)
·
OSTI ID:5532965
CAMEL II 37-pin/7-pin intra-pin fuel injection test
Conference
·
Fri Jun 01 00:00:00 EDT 1984
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6646775
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ALKALI METALS
BREEDER REACTORS
COOLANT LOOPS
COOLING SYSTEMS
ELEMENTS
ENERGY SYSTEMS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLOW BLOCKAGE
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
METALS
REACTOR ACCIDENTS
REACTOR SAFETY EXPERIMENTS
REACTORS
SIMULATION
SODIUM
TRANSIENT OVERPOWER ACCIDENTS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ALKALI METALS
BREEDER REACTORS
COOLANT LOOPS
COOLING SYSTEMS
ELEMENTS
ENERGY SYSTEMS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLOW BLOCKAGE
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
METALS
REACTOR ACCIDENTS
REACTOR SAFETY EXPERIMENTS
REACTORS
SIMULATION
SODIUM
TRANSIENT OVERPOWER ACCIDENTS