| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 1569085 | Journal of Nuclear Materials | 2007 | 9 Pages |
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.
Related Topics
Physical Sciences and Engineering
Energy
Nuclear Energy and Engineering
Authors
S. Teysseyre, Q. Peng, C. Becker, G.S. Was,