Procedures and instrumentation for sodium boiling experiments in EBR-II
The development of instrumentation capable of detecting localized coolant boiling in a liquid metal cooled breeder reactor (LMFBR) has a high priority in fast reactor safety. The detection must be rapid enough to allow corrective action to be taken before significant damage occurs to the core. To develop and test a method of boiling detection, it is desirable to produce boiling in a reactor and thereby introduce a condition in the reactor the original design concepts were chosen to preclude. The proposed boiling experiments are designed to safely produce boiling in the subassembly of a fast reactor and provide the information to develop boiling detection instrumentation without core damage or safety compromise. The experiment consists of the operation of two separate subassemblies, first, a gamma heated boiling subassembly which produces non-typical but highly conservative boiling and then a fission heated subassembly which simulates a prototypical boiling event. The two boiling subassemblies are designed to operate in the instrumentation subassembly test facility (INSAT) of Experiment Breeder Reactor II (EBR-II).
- Research Organization:
- Washington Univ., Seattle (USA)
- DOE Contract Number:
- EY-76-S-05-3363
- OSTI ID:
- 7270371
- Report Number(s):
- TID-27575
- Country of Publication:
- United States
- Language:
- English
Similar Records
Fission heated subassembly for sodium boiling experiments in EBR-II
Validation of the HOTCHAN code for analyzing the EBR-II core following an unprotected loss of flow
Instrumented subassembly system and in-core instrument test facility for EBR-II
Technical Report
·
Wed Dec 31 23:00:00 EST 1975
·
OSTI ID:7270372
Validation of the HOTCHAN code for analyzing the EBR-II core following an unprotected loss of flow
Conference
·
Thu Dec 31 23:00:00 EST 1987
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5852258
Instrumented subassembly system and in-core instrument test facility for EBR-II
Conference
·
Fri Oct 30 23:00:00 EST 1970
·
OSTI ID:4165582
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
ALKALI METALS
BOILING
BOILING DETECTION
BREEDER REACTORS
EBR-2 REACTOR
ELEMENTS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
METALS
PHASE TRANSFORMATIONS
POWER REACTORS
REACTORS
RESEARCH AND TEST REACTORS
SODIUM
SODIUM COOLED REACTORS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ALKALI METALS
BOILING
BOILING DETECTION
BREEDER REACTORS
EBR-2 REACTOR
ELEMENTS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
METALS
PHASE TRANSFORMATIONS
POWER REACTORS
REACTORS
RESEARCH AND TEST REACTORS
SODIUM
SODIUM COOLED REACTORS