(Boiling water reactor (BWR) CORA experiments)
To participate in the 1990 CORA Workshop at Kernforschungszentrum Karlsruhe (KfK) GmbH, Karlsruhe, FRG, on October 1--4, and to participate in detailed discussions on October 5 with the KfK CORA Boiling Water Reactor (BWR) experiments. The traveler attended the 1990 CORA Workshop at KfK, FRG. Participation included the presentation of a paper on work performed by the Boiling Water Reactor Core Melt Progression Phenomena Program at Oak Ridge National Laboratory (ORNL) on posttest analyses of CORA BWR experiments. The Statement of Work (November 1989) for the BWR Core Melt Progression Phenomena Program provides for pretest and posttest analyses of the BWR CORA experiments performed at KfK. Additionally, it is intended that ORNL personnel participate in the planning process for future CORA BWR experiments. For these purposes, meetings were held with KfK staff to discuss such topics as (1) experimental test schedule, (2) BWR test conduct, (3) perceived BWR experimental needs, and (4) KfK operational staff needs with respect to ORNL support. 19 refs.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- Sponsoring Organization:
- NRC
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6434331
- Report Number(s):
- ORNL/FTR-3780; ON: DE91001687
- Country of Publication:
- United States
- Language:
- English
Similar Records
(Installation of a boiling water reactor core melt progression phenomena program)
(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
·
Thu Jun 07 00:00:00 EDT 1990
·
OSTI ID:6954867
(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
A CODES
ACCIDENTS
ALLOYS
BUILDING MATERIALS
BWR TYPE REACTORS
C CODES
CLADDING
COMPUTER CODES
COMPUTERIZED SIMULATION
CONCRETES
CONTAINMENT
CONTAINMENT SYSTEMS
CORIUM
DATA ANALYSIS
DEPOSITION
ENGINEERED SAFETY SYSTEMS
FUEL PELLETS
K CODES
MATERIALS
MEETINGS
MELTDOWN
PELLETS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY EXPERIMENTS
REACTORS
S CODES
SIMULATION
SURFACE COATING
TRAVEL
W CODES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
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
A CODES
ACCIDENTS
ALLOYS
BUILDING MATERIALS
BWR TYPE REACTORS
C CODES
CLADDING
COMPUTER CODES
COMPUTERIZED SIMULATION
CONCRETES
CONTAINMENT
CONTAINMENT SYSTEMS
CORIUM
DATA ANALYSIS
DEPOSITION
ENGINEERED SAFETY SYSTEMS
FUEL PELLETS
K CODES
MATERIALS
MEETINGS
MELTDOWN
PELLETS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY EXPERIMENTS
REACTORS
S CODES
SIMULATION
SURFACE COATING
TRAVEL
W CODES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS