(Integrity of pressure components of nuclear power plants)
The traveler attended the 15th annual MPA Seminar at the University of Stuttgart and the European Symposium on Elastic-Plastic Fracture Mechanics (EPFM) at Freiburg, FRG. Following the symposium the traveler made visits to the IWM Laboratory in Freiburg, FRG, the GKSS Research Center in Geesthacht, FRG, the Welding Institute in Cambridge, UK, and the Structural Integrity Centre at Risley, Warrington, UK. Principal subjects of discussion during the laboratory visits were the measurement of fracture toughness in the upper transition temperature range and the possibility of cooperative analytical and experimental efforts concerning the effects of biaxial stresses on fracture toughness for finite length surface cracks in plates and pressure vessel cylinders.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USNRC
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 5429382
- Report Number(s):
- ORNL/FTR-3437; ON: DE90002654
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
BWR TYPE REACTORS
PRESSURE VESSELS
FRACTURE MECHANICS
MECHANICAL PROPERTIES
PWR TYPE REACTORS
CRACKS
DESIGN
EXPERIMENTAL DATA
FATIGUE
FEDERAL REPUBLIC OF GERMANY
HDR REACTOR
HIGH TEMPERATURE
MEETINGS
PERFORMANCE
PRESSURE EFFECTS
REACTOR SAFETY
RELIABILITY
RESEARCH PROGRAMS
TEMPERATURE EFFECTS
TESTING
TRAVEL
UNITED KINGDOM
WELDING
CONTAINERS
DATA
ENRICHED URANIUM REACTORS
EUROPE
EXPERIMENTAL REACTORS
FABRICATION
INFORMATION
JOINING
MECHANICS
NUMERICAL DATA
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
360103 - Metals & Alloys- Mechanical Properties