Reactor safety program applications and coordination. Task 1. Steam- water mixing program and system hydrodynamics. Quarterly progress report, July--September 1975
Technical Report
·
OSTI ID:4087883
Experimental studies are described which are being conducted to extend the understanding of steam-water interaction phenomena and processes associated with a loss-of-coolant accident. Estimates were made of the degree of steam condensation within the $sup 1$$/$$sub 15$-scale, transparent vessel model during penetration studies conducted with and without cold leg steam. The estimates indicated a high degree of steam condensation within the model. The relationship between water penetration to the lower plenum and annulus pressure loss was investigated to assess and quantify, to the extent possible, the effect of ECC water in the annulus on the resistance to reverse core steam flow of the flow system consisting of the power plenum, downcomer annulus, and broken leg. A preliminary correlation for the penetration data obtained without cold leg steam has been obtained and compared with the experimental data. The correlation relates the water penetration to the reverse core steam flow rate, the ECC injection rate, and the ECC water subcooling. The effect on penetration of operating with cold leg steam was quantified. (auth)
- Research Organization:
- Battelle Columbus Labs., Ohio (USA)
- DOE Contract Number:
- W-7405-ENG-92
- NSA Number:
- NSA-33-019534
- OSTI ID:
- 4087883
- Report Number(s):
- BMI--1940
- Country of Publication:
- United States
- Language:
- English
Similar Records
Reactor safety program applications and coordination. Task 1. Steam--water mixing program and system hydrodynamics. Task 55. Quarterly progress report, January--March 1976. [PWR]
Steam-water mixing and system hydrodynamics program. Task 4. Quarterly progress report, April 1, 1977--June 30, 1977. [PWR]
ECC delivery study: experimental results and discussion
Technical Report
·
Sat May 01 00:00:00 EDT 1976
·
OSTI ID:7351865
Steam-water mixing and system hydrodynamics program. Task 4. Quarterly progress report, April 1, 1977--June 30, 1977. [PWR]
Technical Report
·
Mon Aug 01 00:00:00 EDT 1977
·
OSTI ID:7212700
ECC delivery study: experimental results and discussion
Technical Report
·
Wed Oct 01 00:00:00 EDT 1975
·
OSTI ID:4100979
Related Subjects
*ECCS-- PERFORMANCE TESTING
*LOSS OF COOLANT-- FLUID FLOW
*PWR TYPE REACTORS-- LOSS OF COOLANT
220900* --Nuclear Reactor Technology--Reactor Safety
BLOWDOWN
HYDRODYNAMICS
MIXING
MOCKUP
N77200 --Reactors--Power Reactors
Non-breeding
Light-water Moderated
Non-boiling Water-cooled
N77900* --Reactors--Reactor Safety & Environmental Aspects
REACTOR SAFETY
RESEARCH PROGRAMS
SIMULATION
STEAM
WATER
*LOSS OF COOLANT-- FLUID FLOW
*PWR TYPE REACTORS-- LOSS OF COOLANT
220900* --Nuclear Reactor Technology--Reactor Safety
BLOWDOWN
HYDRODYNAMICS
MIXING
MOCKUP
N77200 --Reactors--Power Reactors
Non-breeding
Light-water Moderated
Non-boiling Water-cooled
N77900* --Reactors--Reactor Safety & Environmental Aspects
REACTOR SAFETY
RESEARCH PROGRAMS
SIMULATION
STEAM
WATER