(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.
- Publication Date:
- OSTI Identifier:
- Report Number(s):
- DOE Contract Number:
- Resource Type:
- Technical Report
- Research Org:
- Oak Ridge National Lab., TN (USA)
- Sponsoring Org:
- Country of Publication:
- United States
- 22 GENERAL STUDIES OF NUCLEAR REACTORS; 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
Enter terms in the toolbar above to search the full text of this document for pages containing specific keywords.