Final report for the flow excursion follow-on testing
The purpose of the Mark 22 Flow Excursion Follow-On testing was to investigate the theory that approximately 15% of the flow bypassed the primary flow channels in previous testing, whereas the design called for only a 3% bypass. The results of the follow-on tests clearly confirmed this theory. The testing was performed in two phases. During the first phase, characterization tests performed during the earlier test program were repeated.
- Research Organization:
- Savannah River Site (SRS), Aiken, SC (United States)
- Sponsoring Organization:
- USDOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC09-89SR18035
- OSTI ID:
- 6589453
- Report Number(s):
- WSRC-TR-93-080; ON: DE93013570
- Country of Publication:
- United States
- Language:
- English
Similar Records
Final report for the flow excursion follow-on testing
Columbia University flow instability experimental program: Volume 6. Single annulus tests, transient test program
Buoyancy-driven flow excursions in fuel assemblies
Technical Report
·
Wed Aug 05 00:00:00 EDT 1992
·
OSTI ID:6589453
Columbia University flow instability experimental program: Volume 6. Single annulus tests, transient test program
Technical Report
·
Tue Sep 01 00:00:00 EDT 1992
·
OSTI ID:6589453
+2 more
Buoyancy-driven flow excursions in fuel assemblies
Conference
·
Sun Dec 31 00:00:00 EST 1995
·
OSTI ID:6589453
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
42 ENGINEERING
22 GENERAL STUDIES OF NUCLEAR REACTORS
FUEL ASSEMBLIES
TESTING
REACTOR ACCIDENTS
SIMULATION
SPECIAL PRODUCTION REACTORS
EXPERIMENTAL DATA
FLOW RATE
FLOWMETERS
LEAKS
PITOT TUBES
PLUGGING
PRESSURE DROP
PROGRESS REPORT
SAVANNAH RIVER PLANT
VENTURI TUBES
ACCIDENTS
DATA
DOCUMENT TYPES
INFORMATION
MEASURING INSTRUMENTS
METERS
NATIONAL ORGANIZATIONS
NUMERICAL DATA
PRODUCTION REACTORS
REACTORS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
210400* - Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated
420200 - Engineering- Facilities
Equipment
& Techniques
220900 - Nuclear Reactor Technology- Reactor Safety
42 ENGINEERING
22 GENERAL STUDIES OF NUCLEAR REACTORS
FUEL ASSEMBLIES
TESTING
REACTOR ACCIDENTS
SIMULATION
SPECIAL PRODUCTION REACTORS
EXPERIMENTAL DATA
FLOW RATE
FLOWMETERS
LEAKS
PITOT TUBES
PLUGGING
PRESSURE DROP
PROGRESS REPORT
SAVANNAH RIVER PLANT
VENTURI TUBES
ACCIDENTS
DATA
DOCUMENT TYPES
INFORMATION
MEASURING INSTRUMENTS
METERS
NATIONAL ORGANIZATIONS
NUMERICAL DATA
PRODUCTION REACTORS
REACTORS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
210400* - Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated
420200 - Engineering- Facilities
Equipment
& Techniques
220900 - Nuclear Reactor Technology- Reactor Safety