Modeling crack-growth processes in fusion-reactor materials

Technical Report · Thu Sep 01 04:00:00 EDT 1983

OSTI ID:5784307

Jones, R H; Wolfer, W G

Models for the effect of the chemical environment on crack-growth processes in austenitic and ferritic stainless were evaluated. The effect of impurity segregation, yield strength, and hydrogen on crack growth of HT-9 and radiation-induced phosphorus segregation on the intergranular stress corrosion of 316SS have been evaluated. Moderate increases in impurity segregation and/or yield strength caused significant decreases in the K/sub IC/ and K/sub TH/ of HT-9, while less than a 10 fold increase in the intergranular stress-corrosion crack-growth rate of 316SS was predicted for a fluence of 100 dpa using the radiation-induced phosphorus segregation data of Brimhall et al. and the stress-corrosion model of Parkins. Therefore, while radiation-induced impurity segregation is greater in 316SS than HT-9, the effect of impurity segregation may be more pronounced in HT-9.

• Research Organization: Pacific Northwest Lab., Richland, WA (USA); Wisconsin Univ., Madison (USA)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 5784307
• Report Number(s): PNL-SA-11425; CONF-830942-12; ON: DE84000477
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
360105* -- Metals & Alloys-- Corrosion & Erosion
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOY-HT-9
ALLOYS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-MOLYBDENUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION
CORROSION RESISTANT ALLOYS
CRACK PROPAGATION
DATA
ELEMENTS
EXPERIMENTAL DATA
FERRITIC STEELS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IMPURITIES
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MECHANICAL PROPERTIES
MOLYBDENUM ALLOYS
NICKEL ALLOYS
NONMETALS
NUMERICAL DATA
PHOSPHORUS
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
STRESS CORROSION
YIELD STRENGTH