(Installation of a boiling water reactor core melt progression phenomena program)
The CORA operational staff at Kernforschungszentrum Karlsruhe (KfK) requested, under the auspices of the Severe Fuel Damage Partners Program, that Oak Ridge National Laboratory (ORNL) developed models, specific to boiling water reactor (BWR) response under severe accident conditions, be applied in support of future BWR experiments to be performed in the CORA facility. Accordingly, the current Statement of Work for the BWR Core Melt Progression Phenomena Program provides for the development of a CORA-specific BWR experimental model to analyze the results of CORA BWR experiments and the planning of future experiments. The traveler installed version 1.0 of the CORA/BWR experiment-specific code on KfK personal computers and assisted the CORA staff in their preliminary pretest analyses for CORA test 18.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- Sponsoring Organization:
- NRC
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6954867
- Report Number(s):
- ORNL/FTR-3629; ON: DE90012195
- Country of Publication:
- United States
- Language:
- English
Similar Records
(Boiling water reactor (BWR) CORA experiments)
(Severe accident technology of BWR (Boiling Water Reactor) reactors)
Development of the BWR Dry Core Initial and Boundary Conditions for the SNL XR2 Experiments
Technical Report
·
Tue Oct 16 00:00:00 EDT 1990
·
OSTI ID:6434331
(Severe accident technology of BWR (Boiling Water Reactor) reactors)
Technical Report
·
Mon Oct 23 00:00:00 EDT 1989
·
OSTI ID:5411859
Development of the BWR Dry Core Initial and Boundary Conditions for the SNL XR2 Experiments
Technical Report
·
Fri Dec 31 23:00:00 EST 1993
·
OSTI ID:787733
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
BWR TYPE REACTORS
C CODES
COMPUTER CODES
COORDINATED RESEARCH PROGRAMS
CORIUM
ENERGY TRANSFER
EUROPE
FEDERAL REPUBLIC OF GERMANY
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
INSTALLATION
MECHANICS
MELTDOWN
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
SAFETY
TRAVEL
WATER COOLED REACTORS
WATER MODERATED REACTORS
WESTERN EUROPE
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
BWR TYPE REACTORS
C CODES
COMPUTER CODES
COORDINATED RESEARCH PROGRAMS
CORIUM
ENERGY TRANSFER
EUROPE
FEDERAL REPUBLIC OF GERMANY
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
INSTALLATION
MECHANICS
MELTDOWN
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
SAFETY
TRAVEL
WATER COOLED REACTORS
WATER MODERATED REACTORS
WESTERN EUROPE