Downcomer effects in a 1/15-scale PWR geometry-experimental data report
Technical Report
·
OSTI ID:7295746
This report presents experimental results obtained in a 1/15-scale cylindrical model of a Pressurized water reactor (PWR) downcomer region at pressures up to 75 psia. These tests are part of a continuing effort to develop analytical tools and predictive techniques to permit calculation of lower plenum filling rates, as a function of time, during a postulated Loss-of-Coolant Accident (LOCA) in PWRs. The effects of countercurrent flow, lower plenum voiding, cold leg steam, and superheated downcomer walls were investigated separately and in combination under test conditions which included elevated vessel pressure, transient steam mass flows (and transient vessel pressure), and coupling of reverse core and cold leg steam flows. A range of geometric and hydraulic parameters was tested including two annulus gap sizes (0.5 and 1.0 inch), a scaled and a deep lower plenum, various ECC water temperatures from 70-212F, ECC water flow rates from 2-180 gpm, and others.
- Research Organization:
- Creare, Inc., Hanover, N.H. (USA)
- OSTI ID:
- 7295746
- Report Number(s):
- PB-268244
- Country of Publication:
- United States
- Language:
- English
Similar Records
ECC delivery study: experimental results and discussion
Analysis of ECC delivery. [PWR]
Effects of cold leg steam and flow baffles on ECC delivery in a simulated multiloop PWR geometry with steam upflow and superheated walls. Quarterly progress report, April 1, 1975--June 30, 1975
Technical Report
·
Wed Oct 01 00:00:00 EDT 1975
·
OSTI ID:4100979
Analysis of ECC delivery. [PWR]
Technical Report
·
Wed Mar 31 23:00:00 EST 1976
·
OSTI ID:7349851
Effects of cold leg steam and flow baffles on ECC delivery in a simulated multiloop PWR geometry with steam upflow and superheated walls. Quarterly progress report, April 1, 1975--June 30, 1975
Technical Report
·
Tue Jul 01 00:00:00 EDT 1975
·
OSTI ID:4156695
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
DATA
ECCS
ENGINEERED SAFETY SYSTEMS
FLOW RATE
FLUID FLOW
FUNCTIONAL MODELS
INFORMATION
LOSS OF COOLANT
PERFORMANCE TESTING
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTORS
SIMULATION
TESTING
TIME DEPENDENCE
TRANSIENTS
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
DATA
ECCS
ENGINEERED SAFETY SYSTEMS
FLOW RATE
FLUID FLOW
FUNCTIONAL MODELS
INFORMATION
LOSS OF COOLANT
PERFORMANCE TESTING
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTORS
SIMULATION
TESTING
TIME DEPENDENCE
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS