Irradiation creep behavior of the fusion heats of HT9 and modified 9Cr-1Mo
Conference
·
OSTI ID:6788860
In-reactor creep data on the fusion heats of HT9 and a modified 9Cr-1Mo steel have been obtained from irradiation of pressurized tube specimens in the FFTF reactor. These irradiations were conducted on specimens which reached /approximately/50 dpa at 400--540/degree/C and which utilized hoop stresses ranging from 0 to 200 Mpa. The creep behavior of these two alloys was found to be similar and to be consistent with creep data on related alloys irradiated in either EBR-II or FFTF. A correlation describing the irradiation-induced creep component of deformation has been developed and compared to the available data. These ferritic steels were also shown to exhibit a superior resistance to creep and swelling at temperatures <520/degree/C when compared to that of the AISI 316 and PCA austenitic alloys also irradiated in the fusion materials program. 18 refs., 5 figs., 2 tabs.
- Research Organization:
- Pacific Northwest Lab., Richland, WA (USA)
- DOE Contract Number:
- AC06-76RL01830; AC06-76FF02170
- OSTI ID:
- 6788860
- Report Number(s):
- PNL-SA-15472; CONF-880613-20; ON: DE88015942
- Country of Publication:
- United States
- Language:
- English
Similar Records
In-reactor creep behavior of the fusion heats of HT9 and modified 9Cr-1Mo
Irradiation creep and swelling of the U.S. fusion heats of HT9 and 9Cr-1Mo to 208 dpa at {approximately}400{degree}C
Fracture toughness data base for HT9 and modified 9Cr-1Mo irradiated in several reactors up to approximately 100 dpa
Conference
·
Tue Oct 01 00:00:00 EDT 1985
·
OSTI ID:5462270
Irradiation creep and swelling of the U.S. fusion heats of HT9 and 9Cr-1Mo to 208 dpa at {approximately}400{degree}C
Technical Report
·
Wed Sep 01 00:00:00 EDT 1993
·
OSTI ID:10110426
Fracture toughness data base for HT9 and modified 9Cr-1Mo irradiated in several reactors up to approximately 100 dpa
Technical Report
·
Sat Jul 01 00:00:00 EDT 1989
·
OSTI ID:5658575
Related Subjects
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360106 -- Metals & Alloys-- Radiation Effects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOY-HT-9
ALLOYS
CHEMICAL COMPOSITION
CHROMIUM ALLOYS
CHROMIUM BASE ALLOYS
CHROMIUM STEELS
CHROMIUM-MOLYBDENUM STEELS
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IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
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PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
STEELS
STRESSES
SWELLING
THERMONUCLEAR REACTOR MATERIALS
360103 -- Metals & Alloys-- Mechanical Properties
360106 -- Metals & Alloys-- Radiation Effects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOY-HT-9
ALLOYS
CHEMICAL COMPOSITION
CHROMIUM ALLOYS
CHROMIUM BASE ALLOYS
CHROMIUM STEELS
CHROMIUM-MOLYBDENUM STEELS
CREEP
FERRITIC STEELS
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
MATERIALS
MECHANICAL PROPERTIES
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
STEELS
STRESSES
SWELLING
THERMONUCLEAR REACTOR MATERIALS