Determination of creep compliance and creep-swelling coupling coefficients for neutron-irradiated titanium-modified stainless steel at @400 degree C

Conference · Fri Nov 01 00:00:00 EST 1991

OSTI ID:5969552

Toloczko, M B ^[1]; Garner, F A ^[2]; Eiholzer, C R ^[3]

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1. California Univ., Berkeley, CA (United States)
2. Pacific Northwest Lab., Richland, WA (United States)
3. Westinghouse Hanford Co., Richland, WA (United States)

Irradiation creep data from FFTF-MOTA at {approximately}400{degrees}C were analyzed for nine 20% cold-worked titanium-modified type 316 stainless steels, each of which exhibits a different duration for the transient regime of swelling. One of these steels was the fusion prime candidate alloy designated PCA. The others were various developmental breeder reactor heats. The analysis was based on the assumption that the B{sub 0} + DS creep model applies to these steels at this temperature. This assumption was found to be valid. A creep-swelling coupling coefficient of D {approx} 0.6 {times} 10{sup {minus}2} MPa{sup {minus}1} was found for all steels that had developed a significant level of swelling. This result is in excellent agreement with the results of earlier studies conducted in EBR-II using annealed AISI 304L and also 10% and 20% cold-worked AISI 316 stainless steels. There appears to be some enhancement of swelling by stress, contradicting an important assumption in the analysis and leading to an apparent but misleading nonlinearity of creep with respect to stress.

• Research Organization: Pacific Northwest Lab., Richland, WA (United States)
• Sponsoring Organization: USDOE; USDOE, Washington, DC (United States)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 5969552
• Report Number(s): PNL-SA-19385; CONF-911111-22; ON: DE92006518
• Resource Relation: Conference: International conference on fusion reactor materials, Clearwater, FL (United States), 17-22 Nov 1991
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
Ma
36 MATERIALS SCIENCE
STAINLESS STEEL-316
DAMAGING NEUTRON FLUENCE
THERMONUCLEAR REACTOR MATERIALS
PHYSICAL RADIATION EFFECTS
CREEP
SWELLING
TITANIUM ALLOYS
ALLOYS
AUSTENITIC STEELS
CHROMIUM ALLOYS
CHROMIUM-NICKEL STEELS
CHROMIUM-NICKEL-MOLYBDENUM STEELS
CORROSION RESISTANT ALLOYS
HEAT RESIS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MECHANICAL PROPERTIES
MOLYBDENUM ALLOYS
NEUTRON FLUENCE
NICKEL ALLOYS
RADIATION EFFECTS
STAINLESS STEELS
STEEL-CR17NI12MO3
STEELS
700480* - Fusion Technology- Component Development
Materials Studies- (1992-)
360106 - Metals & Alloys- Radiation Effects
360103 - Metals & Alloys- Mechanical Properties