In-reactor creep rupture behavior of the D9 alloys
The uncertainties in the in-reactor stress rupture data have been significantly reduced with the acquisition of the Materials Open Test Assembly (MOTA) for testing of materials in the Fast Flux Test Facility (FFTF). The temperature uncertainty associated with irradiation in this vehicle is +- 5/sup 0/C. Moreover, through the use of tag gases and an on-line cover gas monitoring system, on-line detection of specimen ruptures is possible during irradiation, thereby significantly reducing the uncertainty associated with the rupture times. Titanium additions, increases in nickel content and decreases in chromium content, which were made to improve the swelling response of 316 SS, resulted in an alloy class referred to as ''D9''. In-reactor stress rupture data from the MOTA experiment have been reported on two conditions of the D9-type alloys for exposure times corresponding to 2,400 hours at irradiation temperatures of 575, 605, 670, and 750/sup 0/C. For these conditions the in-reactor rupture times were similar to those observed in thermal control tests. This report will describe both the in-reactor stress rupture behavior and the thermal control data for 20% cold work (CW) 316 SS and for 10 and 20% CW D9-type alloy over a similar temperature range for in-reactor exposure times corresponding to 13170 hr. and peak fast fluences corresponding to 17 x 10/sup 22/ n/cm/sup 2/ (E > 0.1 MeV).
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- AC06-76FF02170
- OSTI ID:
- 6296661
- Report Number(s):
- HEDL-SA-3548; CONF-860605-44; ON: DE87011480; TRN: 87-030160
- Resource Relation:
- Conference: 13. international symposium on the effects of radiation on materials, Seattle, WA, USA, 23 Jun 1986; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ALLOY-D-9
CREEP
PHYSICAL RADIATION EFFECTS
REACTOR MATERIALS
RUPTURES
STAINLESS STEEL-316
CRACK PROPAGATION
DATA COVARIANCES
EXPERIMENTAL DATA
FFTF REACTOR
FRACTURE MECHANICS
IRRADIATION
NEUTRON FLUX
STRESSES
THERMAL TESTING
ALLOYS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
DATA
EPITHERMAL REACTORS
FAILURES
FAST REACTORS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
MATERIALS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
NICKEL STEELS
NICKEL-CHROMIUM STEELS
NONDESTRUCTIVE TESTING
NUMERICAL DATA
RADIATION EFFECTS
RADIATION FLUX
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
STAINLESS STEELS
STEELS
TEST REACTORS
TESTING
360103* - Metals & Alloys- Mechanical Properties
220200 - Nuclear Reactor Technology- Components & Accessories
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors