Facility for stress corrosion cracking of irradiated specimens in supercritical water
Source abstract
Abstract
This paper presents the capability to conduct stress corrosion cracking experiments on neutron-irradiated material in supercritical water for application to the GenIV supercritical water reactor concept. The Irradiated Materials Testing Laboratory (IMTL) is dedicated to performing stress corrosion cracking experiments of neutron-irradiated specimens in supercritical water in both content extension rate tensile mode and crack growth rate mode and to conduct analysis of the morphology and composition of the fracture surface via scanning electron microscopy with energy dispersive X-ray analysis.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Subcritical and Supercritical Water Processes · Nuclear Materials and Properties · Heat transfer and supercritical fluids
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (2)
Show source-provided references
1. ASTM E647-95a, Standard Test Method for Measurement of Fatigue Crack Growth Rates, 1995, p. 577.
2. P. Andresen et al., in: Proceedings of 12th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems–Water Reactors, TMS, Warrendale, PA, 2005.