Improving Nuclear Power Plant Safety with FeCrAl Alloy Fuel Cladding. (9th January 2017)

• Record Type: Journal Article
• Authors: Rebak, Raul B.; Terrani, Kurt A.; Gassmann, William P.; Williams, John B.; Ledford, Kevin L.
• Is Part Of: MRS advances. Volume 2:Number 21/22(2017)
• Page Start: 1217
• Page End: 1224
• Publication Date: 2017-01-09
• Subjects: corrosion, -- energy generation, -- nuclear materials; Electrical engineering -- Congresses; Physics -- Congresses; Materials -- Research -- Congresses; Materials science -- Congresses; 620.11
• DOI: 10.1557/adv.2017.5
• Languages: English
• ISSNs: 2059-8521

Abstract

ABSTRACT: The US Department of Energy (DOE) is partnering with fuel vendors to develop enhanced accident tolerant nuclear fuels for Generation III water cooled reactors. In comparison with the standard current uranium dioxide and zirconium alloy system UO2-Zr), the proposed alternative accident tolerant fuel (ATF) should better tolerate loss of cooling in the core for a considerably longer time while maintaining or improving the fuel performance during normal operation conditions. General Electric, Oak Ridge National Laboratory and their partners have proposed to replace zirconium based alloy cladding in current commercial power reactors with an iron-chromium-aluminum (FeCrAl) alloy cladding such as APMT. The use of FeCrAl alloys will greatly reduce the risk of operating the power reactors to produce electricity.