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Influence of neutron fluence and irradiation temperature on the radiation annealing mechanisms of reactor pressure vessel steels

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5045700
None
Research Organization:
KFA-Germany, D-5170 Juelich
OSTI ID:
5045700
Report Number(s):
CONF-810606-
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 38
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
360106* -- Metals & Alloys-- Radiation Effects
ALLOYS
ANNEALING
CONTAINERS
EMBRITTLEMENT
HEAT TREATMENTS
HIGH TEMPERATURE
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS TESTING
MECHANICAL PROPERTIES
NEUTRON FLUENCE
PHYSICAL RADIATION EFFECTS
PRESSURE VESSELS
RADIATION EFFECTS
REACTOR SAFETY
SAFETY
SENSITIVITY
STEELS
TESTING