(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. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USNRC
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6434331
- Report Number(s):
- ORNL/FTR-3780; ON: DE91001687
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
BWR TYPE REACTORS
REACTOR SAFETY EXPERIMENTS
REACTOR ACCIDENTS
COMPUTERIZED SIMULATION
A CODES
C CODES
CLADDING
CONCRETES
CONTAINMENT SYSTEMS
CORIUM
DATA ANALYSIS
FUEL PELLETS
K CODES
MEETINGS
MELTDOWN
REACTOR CORES
S CODES
TRAVEL
W CODES
ZIRCALOY
ACCIDENTS
ALLOYS
BUILDING MATERIALS
COMPUTER CODES
CONTAINMENT
DEPOSITION
ENGINEERED SAFETY SYSTEMS
MATERIALS
PELLETS
REACTOR COMPONENTS
REACTORS
SIMULATION
SURFACE COATING
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
990200 - Mathematics & Computers