Evaluation of IAEA coordinated program steels and welds for 288 deg C radiation embrittlement resistance
Technical Report
·
OSTI ID:5046065
Eight steel materials supplied by the Federal Republic of Germany, France and Japan to the International Atomic Energy Agency (IAEA) Program on 'Analysis of the Behavior of Advanced Reactor Pressure Vessel Steels Under Neutron Irradiation' were irradiated at 288C for assessments of relative notch ductility and dynamic fracture toughness change with approximately 2 x 10 to the 19th power n/sq cm, E >1 MeV. Notch ductility and fracture toughness were determined, respectively, by Charpy-V and fatigue precracked Charpy-V test methods. An A533-B steel plate (HSST 03) produced in the USA was included in the irradiation test series for reference.
- Research Organization:
- Naval Research Lab., Washington, DC (USA)
- OSTI ID:
- 5046065
- Report Number(s):
- NUREG/CR-2487; NRL-MR-4655
- 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
360106* -- Metals & Alloys-- Radiation Effects
ALLOYS
BARYONS
CONTAINERS
DUCTILITY
ELEMENTARY PARTICLES
EMBRITTLEMENT
EVALUATION
FAST NEUTRONS
FERMIONS
FRACTURE PROPERTIES
HADRONS
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
MATERIALS
MECHANICAL PROPERTIES
NEUTRONS
NUCLEONS
PHYSICAL RADIATION EFFECTS
PRESSURE VESSELS
RADIATION EFFECTS
REACTOR MATERIALS
STEEL-ASTM-A533
STEELS
TENSILE PROPERTIES
WELDED JOINTS
220200 -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360106* -- Metals & Alloys-- Radiation Effects
ALLOYS
BARYONS
CONTAINERS
DUCTILITY
ELEMENTARY PARTICLES
EMBRITTLEMENT
EVALUATION
FAST NEUTRONS
FERMIONS
FRACTURE PROPERTIES
HADRONS
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
MATERIALS
MECHANICAL PROPERTIES
NEUTRONS
NUCLEONS
PHYSICAL RADIATION EFFECTS
PRESSURE VESSELS
RADIATION EFFECTS
REACTOR MATERIALS
STEEL-ASTM-A533
STEELS
TENSILE PROPERTIES
WELDED JOINTS