Impact behavior of 9-Cr and 12-Cr ferritic steels after low-temperature irradiation
Conference
·
OSTI ID:6112801
Miniature Charpy impact specimens of 9Cr-1MoVNb and 12Cr-1MoVW steels and these steels with 1 and 2% Ni were irradiated in the High-Flux Isotope Reactor (HFIR) at 50/sup 0/C to displacement damage levels of up to 9 dpa. Nickel was added to study the effect of transmutation helium. Irradiation caused an increase in the ductile-brittle transition temperature (DBTT). The 9Cr-1MoVNb steels, with and without nickel, showed a larger shift than the 12Cr-1MoVW steels, with and without nickel. The results indicated that helium also increased the DBTT. The same steels were previously irradiated at higher temperatures. From the present and past tests, the effect of irradiation temperature on the DBTT behavior can be evaluated. For the 9Cr-1MoVNb steel, there is a continuous decrease in the magnitude of the DBTT increase up to an irradiation temperature of about 400/sup 0/C, after which the shift drops rapidly to zero at about 450/sup 0/C. The DBTT of the 12Cr-1MoVW steel shows a maximum increase at an irradiation temperature of about 400/sup 0/C and less of an increase at either higher or lower irradiation temperatures.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6112801
- Report Number(s):
- CONF-871036-3; ON: DE88000333
- Country of Publication:
- United States
- Language:
- English
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OSTI ID:10115547
Related Subjects
36 MATERIALS SCIENCE
360106 -- Metals & Alloys-- Radiation Effects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOYS
CHARPY TEST
CHROMIUM ALLOYS
DESTRUCTIVE TESTING
ELEMENTS
ENRICHED URANIUM REACTORS
FERRITIC STEELS
FIRST WALL
FLUIDS
GASES
HELIUM
HFIR REACTOR
HIGH TEMPERATURE
IMPACT STRENGTH
IMPACT TESTS
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL TESTS
NICKEL ALLOYS
NONMETALS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
RARE GASES
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
STEELS
TANK TYPE REACTORS
TEST REACTORS
TESTING
THERMAL REACTORS
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TRANSMUTATION
WATER COOLED REACTORS
WATER MODERATED REACTORS
360106 -- Metals & Alloys-- Radiation Effects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOYS
CHARPY TEST
CHROMIUM ALLOYS
DESTRUCTIVE TESTING
ELEMENTS
ENRICHED URANIUM REACTORS
FERRITIC STEELS
FIRST WALL
FLUIDS
GASES
HELIUM
HFIR REACTOR
HIGH TEMPERATURE
IMPACT STRENGTH
IMPACT TESTS
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL TESTS
NICKEL ALLOYS
NONMETALS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
RARE GASES
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
STEELS
TANK TYPE REACTORS
TEST REACTORS
TESTING
THERMAL REACTORS
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TRANSMUTATION
WATER COOLED REACTORS
WATER MODERATED REACTORS