Strength and rupture-life transitions caused by secondary carbide precipitation in HT-9 during high-temperature low-rate mechanical testing
The martensitic-ferritic alloy HT-9 is slated for long-term use as a fuel-cladding material in the Integral Fast Reactor. Analysis of published high-temperature mechanical property data suggests that secondary carbide precipitation would occur during service life causing substantial strengthening of the as-heat-treated material. Aspects of the kinetics of this precipitation process are extracted from calculations of the back stress necessary to produce the observed strengthening effect under various creep loading conditions. The resulting Arrhenius factor is shown to agree quantitatively with shifts to higher strength of crept material in reference to the intrinsic strength of HT-9. The results of very low constant strain-rate high-temperature tensile tests on as-heat-treated HT-9 that focus on the transition in strength with precipitation will be presented and related to rupture-life.
- Research Organization:
- Argonne National Lab., IL (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 10103613
- Report Number(s):
- ANL/RE/CP-75828; CONF-921109-3; ON: DE93002917; TRN: 93:001060
- Resource Relation:
- Conference: Fall meeting of the Metallurgical Society and American Institute of Metallurgical and Petroleum Engineers,Chicago, IL (United States),1-5 Nov 1992; Other Information: PBD: [1992]
- Country of Publication:
- United States
- Language:
- English
Similar Records
Machine Learning Augmented Predictive and Generative Model for Rupture Life in Ferritic and Austenitic Steels
Microstructural evolution in a ferritic-martensitic stainless steel and its relation to high-temperature deformation and rupture models
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ALLOY-HT-9
MECHANICAL PROPERTIES
AGE HARDENING
RUPTURES
CREEP
STRAIN RATE
TENSILE PROPERTIES
ACTIVATION ENERGY
TEMPERATURE RANGE 0400-1000 K
CORRELATIONS
CARBIDES
PRECIPITATION HARDENING
IFR REACTOR
FUEL CANS
TEMPERATURE RANGE 1000-4000 K
AGING
MICROSTRUCTURE
360103
210500
POWER REACTORS
BREEDING