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Irradiation Assisted Stress Corrosion and Cracking
Irradiated in 1990
- Tested the effects of coolant chemistry on IASCC of BWR alloys.
- Compared slow strain rate test results using representative (irradiated) coolant in a fast neutron flux to post-irradiation test results.
- Unique feature of loop: specimens actively loaded in a BWR coolant environment in core using a feedback controlled mechanical test machine.
- Specimens pre-irradiated in a controlled temperature inert gas environment.
- Load, displacement and water chemistry conditions monitored and controlled during testing.
- Post-irradiation SEM fractography of specimens.
- Mechanical property test specimen was actively loaded in-core with water chemistry and temperatures simulating BWR conditions. The rig was configured for this experiment for slow strain rate testing at strain rates down to about 10-7/s using a ball-screw loading machine. An in-core platinum electrode and out-of-core external reference Ag/AgCl electrodes were used to measure the electrochemical corrosion potential of the specimen. The IASCC-SSRT is available for routine operation.
In-Core Constant Load Test Rig (UNCLTIC)
The uniaxial constant load test in core (UNCLTIC) facility is a series of ten mechanical property test specimens that are actively loaded with five in core specimens and five out of core specimens for direct in-flux and ex-flux comparisons under water chemistry conditions simulating BWR conditions. The specimens are loaded to yield and held until failure.
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