Loss-of-flow-without-scram tests in Experimental Breeder Reactor-II and comparison with pretest predictions
This article discusses a series of successful loss-of-flow-without-scram tests conducted in Experimental Breeder Reactor-II (EBR-II), a metal-fueled, sodium-cooled fast reactor. These May 1985 tests demonstrated the capability of the EBR to reduce reactor power passively during a loss of flow and to maintain reactor temperatures within bounds without any reliance on an active safety system. The tests were run from reduced power to ensure that temperatures could be maintained well below the fuel-clad eutectic temperature. Good agreement was found between selected test data and pretest predictions made with the EBR-II system analysis code NATDEMO and the hot channel analysis code HOTCHAN. The article also discusses safety assessments of the tests as well as modifications required on the EBR-II reactor safety system for conducting required on the EBR-II reactor safety system for the conducting the tests.
- Research Organization:
- Argonne National Lab., IL
- OSTI ID:
- 5982017
- Journal Information:
- Nucl. Saf.; (United States), Vol. 28:2
- Country of Publication:
- United States
- Language:
- English
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EBR-2 REACTOR
LOSS OF FLOW
REACTOR SAFETY EXPERIMENTS
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ENGINEERED SAFETY SYSTEMS
FAILURES
H CODES
HEAT TRANSFER
HYDRAULICS
PRIMARY COOLANT CIRCUITS
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REACTOR CORES
REACTOR INSTRUMENTATION
REACTOR SHUTDOWN
TIME DEPENDENCE
TRANSIENTS
ACCIDENTS
BREEDER REACTORS
COMPUTER CODES
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EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
LIQUID METAL COOLED REACTORS
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REACTOR COMPONENTS
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220900* - Nuclear Reactor Technology- Reactor Safety
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