Measurement of two-phase flow at the core/upper plenum interface for a PWR geometry under simulated reflood conditions
Technical Report
·
OSTI ID:5870328
The Instrument Development Loop (IDL) Program is part of the International 2D/3D Refill and Reflood Experimental and Analytical Research Program. Among the objectives of the International Program are: the study of the steam binding effect during reflood flow distribution (chimney effect) in a heated core; and the study of flow hydrodynamics in the core, downcomer and upper plenum during refill and reflood. Three experimental facilities were used in these studies: a one-bundle air/water loop, a three-bundle air/water loop, and a one-bundle steam/water loop. The loops represent full-scale vertical sections of the UPTF, extending from spray nozzles to the top of the upper plenum and including a short length of dummy fuel rods, upper end boxes, core support plate and control rod guide tubes. Three flow regimes were identified and studied: (1) all liquid down; (2) countercurrent flow in which gas (or vapor) goes up and liquid goes both up and down; and (3) cocurrent flow in which both gas (or vapor) and liquid go up.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5870328
- Report Number(s):
- NUREG/CR-3138; ORNL/TM-8204; ON: DE83016432
- Country of Publication:
- United States
- Language:
- English
Similar Records
Measurement of two-phase flow at the core upper plenum interface under simulated reflood conditions. [PWR; BWR]
Instrumentation development for low range, long line differential pressure measurements
Application of UPTF data for modeling liquid draindown in the downcomer region of a PWR using RELAP5/MOD2-B&W
Conference
·
Wed Dec 31 23:00:00 EST 1980
·
OSTI ID:5715966
Instrumentation development for low range, long line differential pressure measurements
Journal Article
·
Thu Dec 31 23:00:00 EST 1981
· ISA Trans.; (United States)
·
OSTI ID:5935760
Application of UPTF data for modeling liquid draindown in the downcomer region of a PWR using RELAP5/MOD2-B&W
Technical Report
·
Fri Sep 01 00:00:00 EDT 1995
·
OSTI ID:107763
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
CALIBRATION
DATA
DENSITOMETERS
ENERGY TRANSFER
EXPERIMENTAL DATA
FLOWMETERS
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
INFORMATION
LOSS OF COOLANT
MEASURING INSTRUMENTS
MECHANICS
METERS
NUMERICAL DATA
PHOTOMETERS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR INTERNALS
REACTOR SAFETY
REACTORS
SAFETY
TEST FACILITIES
TWO-PHASE FLOW
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
CALIBRATION
DATA
DENSITOMETERS
ENERGY TRANSFER
EXPERIMENTAL DATA
FLOWMETERS
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
INFORMATION
LOSS OF COOLANT
MEASURING INSTRUMENTS
MECHANICS
METERS
NUMERICAL DATA
PHOTOMETERS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR INTERNALS
REACTOR SAFETY
REACTORS
SAFETY
TEST FACILITIES
TWO-PHASE FLOW
WATER COOLED REACTORS
WATER MODERATED REACTORS