(Computational analysis of dynamic crack run-arrest phenomena in reactor pressure vessel steels)
The traveler visited Kernforschungszentrum Karlsruhe (KFK), Federal Republic of Germany (FRG) to confer with Dr. H.K. Stamm and other staff members to accomplish several objectives that relate to the computational analysis of dynamic crack run-arrest phenomena in reactor implementation which is the product of approximately three years of KFK work in the area of unified constitutive theories for rate-dependent materials. In exchange, the traveler would discuss with KFK a computer implementation of five elastic and inelastic candidate fracture parameters utilized in the ORNL ADINA computer program for elasto-dynamic and viscoplastic-dynamic fracture analysis. An essential feature of this exchange would be in-depth discussions with the KFK staff concerning implementation, application, and future development of these computational techniques.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- Sponsoring Organization:
- NRC
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 5688714
- Report Number(s):
- ORNL/FTR-2526; ON: DE89017294
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
CONTAINERS
CRACK PROPAGATION
EUROPE
FEDERAL REPUBLIC OF GERMANY
FRACTURE PROPERTIES
IRON ALLOYS
IRON BASE ALLOYS
MECHANICAL PROPERTIES
PRESSURE VESSELS
REACTOR VESSELS
STEELS
THERMAL SHOCK
TRAVEL
WESTERN EUROPE
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
CONTAINERS
CRACK PROPAGATION
EUROPE
FEDERAL REPUBLIC OF GERMANY
FRACTURE PROPERTIES
IRON ALLOYS
IRON BASE ALLOYS
MECHANICAL PROPERTIES
PRESSURE VESSELS
REACTOR VESSELS
STEELS
THERMAL SHOCK
TRAVEL
WESTERN EUROPE