Critical flow through a small break on a large pipe with stratified flow
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5691799
An experimental investigation of critical steam-water two-phase flow through a small break on a horizontal pipe carrying a stratified two-phase flow has been carried out. This flow configuration may occur in small-break light water reactor (LWR) accidents. The critical discharge depends on the effective stagnation state of the fluid entering the break channel and this state is in turn dependent on the orientation of the break (up, down, side) and the proximity of the free surface in the upstream stratified region.
- Research Organization:
- Univ. of California, Berkeley
- OSTI ID:
- 5691799
- Report Number(s):
- CONF-851115-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 50
- Country of Publication:
- United States
- Language:
- English
Similar Records
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Journal Article
·
Wed Oct 31 23:00:00 EST 1984
· Nucl. Sci. Eng.; (United States)
·
OSTI ID:6280418
Small break critical discharge: The roles of vapor and liquid entrainment in a stratified two-phase region upstream of the break
Technical Report
·
Sun Nov 30 23:00:00 EST 1986
·
OSTI ID:7010091
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Journal Article
·
Sat Nov 30 23:00:00 EST 1996
· International Communications in Heat and Mass Transfer
·
OSTI ID:418045
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210100 -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
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42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
ACCIDENTS
BWR TYPE REACTORS
CRITICAL FLOW
ENERGY TRANSFER
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FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PIPES
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY EXPERIMENTS
REACTORS
RUPTURES
STRATIFICATION
TWO-PHASE FLOW
WATER COOLED REACTORS
WATER MODERATED REACTORS