IRRADIATION EFFECTS IN STRAIN AGED PRESSURE VESSEL STEEL
Technical Report
·
OSTI ID:4787011
Tensile specimens, Charpy-V notch and subsize im pact specimens of an Al killed carbon manganese steel, were irradiated at 160 to 190 deg C in the reactor G1. The total neutron dose received was 2.4 x 10/sup 18/ n/cm/sup 2/ (>1 Mev). Specimens were prepared from normalized plate and from strain aged material from the same plate. It was found that the changes in brittle ductile transition temperature due to neutron irradiation and those due to strain ageing must be considered additive. (auth)
- Research Organization:
- Aktiebolaget Atomenergi, Stockholm
- NSA Number:
- NSA-16-016773
- OSTI ID:
- 4787011
- Report Number(s):
- AE-65
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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Related Subjects
AGING
ALUMINUM ALLOYS
BRITTLENESS
CARBON STEELS
DEFORMATION
DUCTILITY
FAST NEUTRONS
HARDNESS
HEAT TREATMENTS
IMPACT SHOCK
IRRADIATION
MANGANESE ALLOYS
METALS, CERAMICS, AND OTHER MATERIALS
NEUTRON BEAMS
PLATES
PRESSURE VESSELS
RADIATION DOSES
RADIATION EFFECTS
REDUCTION
SAMPLING
STEELS
TEMPERATURE
TENSILE PROPERTIES
TRANSITION TEMPERATURE
ALUMINUM ALLOYS
BRITTLENESS
CARBON STEELS
DEFORMATION
DUCTILITY
FAST NEUTRONS
HARDNESS
HEAT TREATMENTS
IMPACT SHOCK
IRRADIATION
MANGANESE ALLOYS
METALS, CERAMICS, AND OTHER MATERIALS
NEUTRON BEAMS
PLATES
PRESSURE VESSELS
RADIATION DOSES
RADIATION EFFECTS
REDUCTION
SAMPLING
STEELS
TEMPERATURE
TENSILE PROPERTIES
TRANSITION TEMPERATURE