Ultrasonic dynamic imaging (UDI) system to determine the size and velocity of large spherical simulated bubbles in liquids. [LMFBR]
Conference
·
OSTI ID:5591642
As part of the nuclear safety program it is desirable to fully characterize the dynamics of a vapor bubble formed in liquid sodium. The bubble would be formed during the hypothetical case of partial core vaporization in a liquid-metal reactor. A real-time ultrasonic imaging system was developed which provides simultaneous measurement of the rise velocity and radius of large spherical bubbles. The range of applicability of the UDI system has been determined in model experiments.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5591642
- Report Number(s):
- CONF-791008-5; TRN: 80-007954
- Resource Relation:
- Conference: ASNT fall conference, St Louis, MO, USA, 15 Oct 1979
- Country of Publication:
- United States
- Language:
- English
Similar Records
Development of an ultrasonic imaging system to measure the size and velocity of large bubbles rising through liquids
General formulation of an HCDA bubble rising in a sodium pool and the effect of nonequilibrium on fuel transport. [LMFBR]
Condensation from a large HCDA vapor-gas bubble onto structures. [LMFBR]
Technical Report
·
Tue Apr 01 00:00:00 EST 1980
·
OSTI ID:5591642
+1 more
General formulation of an HCDA bubble rising in a sodium pool and the effect of nonequilibrium on fuel transport. [LMFBR]
Technical Report
·
Tue Jan 01 00:00:00 EST 1980
·
OSTI ID:5591642
Condensation from a large HCDA vapor-gas bubble onto structures. [LMFBR]
Conference
·
Sun Jan 01 00:00:00 EST 1978
·
OSTI ID:5591642
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LMFBR TYPE REACTORS
REACTOR PROTECTION SYSTEMS
REACTOR INSTRUMENTATION
ULTRASONIC TESTING
BUBBLES
PRIMARY COOLANT CIRCUITS
REACTOR CORE DISRUPTION
REACTOR SAFETY
SODIUM
SPECIFICATIONS
TWO-PHASE FLOW
ACCIDENTS
ACOUSTIC TESTING
ALKALI METALS
BREEDER REACTORS
COOLING SYSTEMS
ELEMENTS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
LIQUID METAL COOLED REACTORS
MATERIALS TESTING
METALS
NONDESTRUCTIVE TESTING
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SAFETY
TESTING
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LMFBR TYPE REACTORS
REACTOR PROTECTION SYSTEMS
REACTOR INSTRUMENTATION
ULTRASONIC TESTING
BUBBLES
PRIMARY COOLANT CIRCUITS
REACTOR CORE DISRUPTION
REACTOR SAFETY
SODIUM
SPECIFICATIONS
TWO-PHASE FLOW
ACCIDENTS
ACOUSTIC TESTING
ALKALI METALS
BREEDER REACTORS
COOLING SYSTEMS
ELEMENTS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
LIQUID METAL COOLED REACTORS
MATERIALS TESTING
METALS
NONDESTRUCTIVE TESTING
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SAFETY
TESTING
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding