Irradiation-assisted stress corrosion cracking of fusion reactor material

Conference · Wed Aug 01 04:00:00 EDT 1990

OSTI ID:6308022

Jones, R H; Simonen, E P; Bruemmer, S M

Irradiation-assisted stress-corrosion cracking (IASCC) is a phenomenon produced by radiation-induced alterations in the material and environment. These alternations include radiation-induced segregation and depletion of specific elements at grain boundaries, radiation creep and hardening and radiolytic effects induced in the aqueous environment. This phenomenon has been clearly identified as an active crack growth mechanism for in-core components in fission reactor must be considered as a potential crack growth mechanism for water-cooled fusion reactors such as ITER or power reactors. The potential for IASCC phenomenon occurring in ITER structural materials is being evaluated by modeling and experiment. Results from modeling calculations for impurity segregation at ITER-relevant temperatures have been completed and suggest that this phenomenon is not likely to induce IASCC during the ITER design life. If a fusion power reactor is water cooled, IASCC is a definite concern for austenitic stainless steels. It has been clearly demonstrated with modeling and experimental measurements that Cr depletion occurs within about 1 dpa. Phosphorus and Si grain boundary segregation can also occur at this same dose and temperature but their effect on IASCC appears to be secondary to Cr depletion. Also, irradiation creep-induced crack tip strain appears to be a secondary effect. However, there are a number of unexplained observations in the literature on IASCC which may be caused by radiation damage effects other than Cr depletion or impurity segregation.

• Research Organization: Pacific Northwest Lab., Richland, WA (USA)
• Sponsoring Organization: DOE/ER
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 6308022
• Report Number(s): PNL-SA-18469; CONF-9009264--3; ON: DE91005841
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
360106 -- Metals & Alloys-- Radiation Effects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOYS
AUSTENITIC STEELS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CHROMIUM-NICKEL STEELS
CHROMIUM-NICKEL-MOLYBDENUM STEELS
CLOSED PLASMA DEVICES
CORROSION
CORROSION RESISTANT ALLOYS
CRACK PROPAGATION
CRACKS
CREEP
CRYSTAL STRUCTURE
GRAIN BOUNDARIES
HEAT RESIS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH ALLOY STEELS
HYDROGEN COMPOUNDS
IRON ALLOYS
IRON BASE ALLOYS
ITER TOKAMAK
MATERIALS
MECHANICAL PROPERTIES
MICROSTRUCTURE
MOLYBDENUM ALLOYS
NICKEL ALLOYS
OXYGEN COMPOUNDS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
STAINLESS STEEL-304
STAINLESS STEEL-316
STAINLESS STEELS
STEEL-CR17NI12MO3
STEEL-CR19NI10
STEELS
STRESS CORROSION
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTOR MATERIALS
TOKAMAK DEVICES
WATER