Effects of sleeve blockages on axial velocity and intensity of turbulence in an unheated 7 x 7 rod bundle. [PWR]
An experimental study is described which was performed to investigate the turbulent flow phenomena near postulated sleeve blockages in a model nuclear fuel rod bundle. The sleeve blockages were characteristic of fuel clad ''swelling'' or ''ballooning'' which could occur during loss-of-coolant accidents (LOCA) in pressurized water reactors. The study was conducted to provide information relative to the flow phenomena near postulated blockages to support detailed safety analyses of LOCAs. The results of the study are especially useful for verification of the hydraulic treatment of reactor core computer programs such as COBRA.
- Research Organization:
- Battelle Pacific Northwest Labs., Richland, Wash. (USA)
- DOE Contract Number:
- E(45-1)-1830
- OSTI ID:
- 7290924
- Report Number(s):
- BNWL-1965
- Country of Publication:
- United States
- Language:
- English
Similar Records
Effects of sleeve blockages on air velocity distributions in an unheated 7 x 7 rod bundle. [PWR]
Air velocity profiles near sleeve blockages in an unheated 7 x 7 rod bundle. [PWR]
Evaluation of flow redistribution due to flow blockage in rod bundles using COBRA code simulation. Final report. [PWR]
Technical Report
·
Wed Dec 31 23:00:00 EST 1975
·
OSTI ID:7195920
Air velocity profiles near sleeve blockages in an unheated 7 x 7 rod bundle. [PWR]
Conference
·
Sat Mar 31 23:00:00 EST 1979
·
OSTI ID:5713044
Evaluation of flow redistribution due to flow blockage in rod bundles using COBRA code simulation. Final report. [PWR]
Technical Report
·
Wed Dec 31 23:00:00 EST 1980
·
OSTI ID:6941932
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
FLOW BLOCKAGE
FLOW RATE
FLUID FLOW
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
LOSS OF COOLANT
MOCKUP
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
SIMULATION
STRUCTURAL MODELS
TURBULENCE
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
FLOW BLOCKAGE
FLOW RATE
FLUID FLOW
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
LOSS OF COOLANT
MOCKUP
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
SIMULATION
STRUCTURAL MODELS
TURBULENCE
WATER COOLED REACTORS
WATER MODERATED REACTORS