In-vessel instrumentation for high-temperature transient two-phase flows
Conference
·
OSTI ID:5658680
A program was initiated in 1977 to develop instrumentation for measurement of in-vessel local fluid phenomena in safety experiments designed to investigate the refill and reflood phases of the PWR loss-of-coolant accident. Objective is to develop techniques and systems for measuring fluid flow in-core, deentrainment in the upper plenum, liquid fallback from the upper plenum into the core, and flow across the core-upper plenum interface.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5658680
- Report Number(s):
- CONF-801053-13; ON: DE84003321
- Country of Publication:
- United States
- Language:
- English
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Conference
·
Sun Dec 31 23:00:00 EST 1978
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OSTI ID:6069174
Reflood instrumentation development at ORNL: a status report
Conference
·
Sat Dec 31 23:00:00 EST 1977
·
OSTI ID:6348393
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Journal Article
·
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· ISA Trans.; (United States)
·
OSTI ID:5935760
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
440300 -- Miscellaneous Instruments-- (-1989)
47 OTHER INSTRUMENTATION
ACCIDENTS
FLUID FLOW
LOSS OF COOLANT
MEASURING INSTRUMENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY EXPERIMENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
440300 -- Miscellaneous Instruments-- (-1989)
47 OTHER INSTRUMENTATION
ACCIDENTS
FLUID FLOW
LOSS OF COOLANT
MEASURING INSTRUMENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY EXPERIMENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS