NSUF 24-4950: Post-test tensile fractography and microstructure of HT-9 alloys following ATR irradiation to doses between 0.01 and 10 dpa at 300, 450 and 550°C

The objective of this program is to investigate the strain hardening and fracture characteristics of tested (failed) irradiated tensile specimens of HT-9. The tensile properties of HT-9 following neutron irradiation in the Advanced Test Reactor (ATR) to target doses between 0.01 dpa to 10 dpa at target temperatures of 300, 450, and 550C were measured in June 2022 at ORNL. These specimens are the highest neutron dose alloys for this alloy heat currently available. This particular heat is the same one that was irradiated in the last Phénix experiments to much higher doses, however, those specimens are still not available. Post-irradiation microstructural examination (PIE) of nearly all of the neutron irradiation exposures have been completed in a previous NEUP project. Those samples correspond directly to the tensile irradiation conditions in the recent ORNL tensile tests. The PIE experiments proposed here are to examine the failed tensile specimens for fractography and other aspects of the tensile deformation process. This information will be a major addition to the understanding of the tensile behavior of an alloy, HT9, which is of high interest for advanced reactor applications. This work also fills a large gap in the irradiation landscape for this alloy between ~350C and 600C over a range of doses from 0.01 to 10 dpa.

추가 정보

필드	값
Award Announced Date	2024-05-28T17:04:13.38
Awarded Institution	University of Illinois at Urbana-Champaign
Facility Tech Lead	Kory Linton
Irradiation Facility
PI	Mahmud Hasan Ovi
PI Email	[email protected]
Project Type	RTE
RTE Number	None