Reflooding phenomena of German PWR estimated from CCTF (Cylindrical Core Test Facility), SCTF (Slab Core Test Facility) and UPTF (Upper Plenum Test Facility) results
Conference
·
OSTI ID:6557014
The reflooding behavior in a PWR with a combined injection type ECCS was studied by comparing the test results from Cylindrical Core Test Facility (CCTF), Slab Core Test Facility (SCTF) and Upper Plenum Test Facility (UPTF). Core thermal-hydraulics is discussed mainly based on SCTF test data. In addition, the water accumulation behavior in hot legs and the break-through characteristics at tie plate are discussed.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Regulatory Research; Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 6557014
- Report Number(s):
- NUREG/CP-0091-Vol.4-Add.; CONF-8710111-Vol.4-Add.; ON: TI89001586
- Country of Publication:
- United States
- Language:
- English
Similar Records
TRAC analyses for CCTF and SCTF tests and UPTF design/operation. [Cylindrical Core Test Facility; Slab Core Test Facility; Upper Plenum Test Facility]
TRAC analysis of upper plenum thermal-hydraulic phenomena in the slab core test facility
Reactor safety issues resolved by the 2D/3D Program. International Agreement Report
Conference
·
Mon Dec 31 23:00:00 EST 1984
·
OSTI ID:6411831
TRAC analysis of upper plenum thermal-hydraulic phenomena in the slab core test facility
Conference
·
Tue Dec 31 23:00:00 EST 1985
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6907155
Reactor safety issues resolved by the 2D/3D Program. International Agreement Report
Technical Report
·
Thu Jul 01 00:00:00 EDT 1993
·
OSTI ID:10177080
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
COOLING SYSTEMS
DATA
ECCS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
EUROPE
EXPERIMENTAL DATA
FEDERAL REPUBLIC OF GERMANY
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
INFORMATION
JAERI
JAPANESE ORGANIZATIONS
MECHANICS
NATIONAL ORGANIZATIONS
NUMERICAL DATA
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
TEST FACILITIES
WATER COOLED REACTORS
WATER MODERATED REACTORS
WESTERN EUROPE
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900 -- Nuclear Reactor Technology-- Reactor Safety
COOLING SYSTEMS
DATA
ECCS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
EUROPE
EXPERIMENTAL DATA
FEDERAL REPUBLIC OF GERMANY
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
INFORMATION
JAERI
JAPANESE ORGANIZATIONS
MECHANICS
NATIONAL ORGANIZATIONS
NUMERICAL DATA
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
TEST FACILITIES
WATER COOLED REACTORS
WATER MODERATED REACTORS
WESTERN EUROPE