Experimental Breeder Reactor II (EBR-II): Instrumentation for core surveillance
Conference
·
OSTI ID:7013773
EBR-II has operated for 25 years in support of several major programs. During this time period, several of the original, non-replaceable, flow sensors, RDT sensors and thermocouples have failed in the primary system. This has led to the development of new sensors and the use of calculated values using computer models of the plant. It is important for the next generation of LMR reactors to minimize or eliminate the use of non-replaceable sensors. EBR-II is perhaps the best modeled reactor in the world, thanks to a dedicated T-H analysis program. The success of this program relied on excellent measurements of temperature and flow in subassemblies in the core. The instrumented subassemblies of the XX series provided that measurement capability. From this test series, EBR-II calculations showed that the core could withstand a loss-of-flow without scram accident and a loss-of-heat sink without scram accident from full reactor power without core damage. From this, reactor designers can now design with confidence, inherently safe reactors. 11 refs., 8 figs.
- Research Organization:
- Argonne National Lab., Idaho Falls, ID (USA)
- Sponsoring Organization:
- DOE/NE
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 7013773
- Report Number(s):
- CONF-891286-1; ON: DE90010474
- Country of Publication:
- United States
- Language:
- English
Similar Records
SASSYS validation with the EBR-II (Experimental Breeder Reactor II) shutdown heat removal tests
Results and implications of the EBR-II inherent safety demonstration tests
Demonstration of passive safety features in EBR-II
Conference
·
Tue Oct 31 23:00:00 EST 1989
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:5486959
Results and implications of the EBR-II inherent safety demonstration tests
Conference
·
Wed Dec 31 23:00:00 EST 1986
·
OSTI ID:6770302
Demonstration of passive safety features in EBR-II
Conference
·
Wed Dec 31 23:00:00 EST 1986
·
OSTI ID:6174616
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
220900 -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
COOLING SYSTEMS
EBR-2 REACTOR
ENERGY SYSTEMS
ENERGY TRANSFER
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MEASURING INSTRUMENTS
MECHANICS
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR INSTRUMENTATION
REACTOR MONITORING SYSTEMS
REACTOR SAFETY
REACTORS
REMOTE SENSING
RESEARCH AND TEST REACTORS
SAFETY
SODIUM COOLED REACTORS
SURVEILLANCE
THERMOCOUPLES
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
220900 -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
COOLING SYSTEMS
EBR-2 REACTOR
ENERGY SYSTEMS
ENERGY TRANSFER
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MEASURING INSTRUMENTS
MECHANICS
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR INSTRUMENTATION
REACTOR MONITORING SYSTEMS
REACTOR SAFETY
REACTORS
REMOTE SENSING
RESEARCH AND TEST REACTORS
SAFETY
SODIUM COOLED REACTORS
SURVEILLANCE
THERMOCOUPLES