NSUF 20-19076: Investigation of Degradation Mechanisms of Cr coated Zirconium alloy cladding in Reactive Initiate Accidents (RIA)

Researchers will investigate the thermal, mechanical, and irradiation response of chromium-coated zirconium alloy claddings under RIA conditions, in comparison to uncoated Zr-alloy cladding. The outcome of the project will be used for anticipated licensing applications to the U.S. Nuclear Regulatory Commission (NRC), thereby accelerating use of coated accident tolerant fuel concepts in U.S. commercial power reactors.

Додатне информације

Поље Вредност
Awarded Institution University of Wisconsin
CINR Number 20-19076
Embargo End Date 2029-11-02
Facility Tech Lead Alina Montrose
Irradiation Facilities Advanced Test Reactor
NSUF Call FY 2020 CINR
PI Hwasung Yeom
PIE Facilities Hot Fuel Examination Facility
Project Member Dr. Hwasung Yeom - Pohang University of Science and Technology (POSTECH)
Project Notes Awarded on 11/02/2021
Project Type CINR