Loss-of-flow-without-scram tests in Experimental Breeder Reactor-II and comparison with pretest predictions
Journal Article
·
· Nucl. Saf.; (United States)
OSTI ID:5982017
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), Journal Name: Nucl. Saf.; (United States) Vol. 28:2; ISSN NUSAA
- Country of Publication:
- United States
- Language:
- English
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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
AFTER-HEAT REMOVAL
BREEDER REACTORS
COMPUTER CODES
COOLING SYSTEMS
DESIGN
EBR-2 REACTOR
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAILURES
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
H CODES
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MECHANICS
POWER REACTORS
PRIMARY COOLANT CIRCUITS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR INSTRUMENTATION
REACTOR SAFETY EXPERIMENTS
REACTOR SHUTDOWN
REACTORS
REMOVAL
RESEARCH AND TEST REACTORS
SHUTDOWNS
SODIUM COOLED REACTORS
TIME DEPENDENCE
TRANSIENTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AFTER-HEAT REMOVAL
BREEDER REACTORS
COMPUTER CODES
COOLING SYSTEMS
DESIGN
EBR-2 REACTOR
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAILURES
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
H CODES
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MECHANICS
POWER REACTORS
PRIMARY COOLANT CIRCUITS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR INSTRUMENTATION
REACTOR SAFETY EXPERIMENTS
REACTOR SHUTDOWN
REACTORS
REMOVAL
RESEARCH AND TEST REACTORS
SHUTDOWNS
SODIUM COOLED REACTORS
TIME DEPENDENCE
TRANSIENTS