Light Water Reactor Sustainability Program Status of Silicon Carbide Joining Technology Development

Bragg-Sitton, Shannon M.

Idaho National Laboratory

关键词: 11 Nuclear Fuel Cycle And Fuel Materials;    Nuclear Fuel Cladding;    36 Materials Science Accident Tolerant Fuel;    Accident Tolerant Fuel;    Silicon Carbide;   

DOI  :  10.2172/1122120
RP-ID  :  INL/EXT-13-30268
RP-ID  :  DE-AC07-05ID14517
RP-ID  :  1122120

美国|英语

来源: UNT Digital Library

【 摘 要 】

Advanced, accident tolerant nuclear fuel systems are currently being investigated for potential application in currently operating light water reactors (LWR) or in reactors that have attained design certification. Evaluation of potential options for accident tolerant nuclear fuel systems point to the potential benefits of silicon carbide (SiC) relative to Zr-based alloys, including increased corrosion resistance, reduced oxidation and heat of oxidation, and reduced hydrogen generation under steam attack (off-normal conditions). If demonstrated to be applicable in the intended LWR environment, SiC could be used in nuclear fuel cladding or other in-core structural components. Achieving a SiC-SiC joint that resists corrosion with hot, flowing water, is stable under irradiation and retains hermeticity is a significant challenge. This report summarizes the current status of SiC-SiC joint development work supported by the Department of Energy Light Water Reactor Sustainability Program. Significant progress has been made toward SiC-SiC joint development for nuclear service, but additional development and testing work (including irradiation testing) is still required to present a candidate joint for use in nuclear fuel cladding.