Development of ASTM Standard for SiC-SiC Joint Testing Final Scientific/Technical Report

Jacobsen, George¹  Back, Christina¹ 

[1] General Atomics, San Diego, CA (United States)

关键词: Silicon Carbide;    Cladding;    Joint;    End Plug;    Testing;    Ceramic;   

DOI  :  10.2172/1224811
RP-ID  :  DOE--A28213
PID  :  OSTI ID: 1224811
Others  :  Other: GA A28213

学科分类：核能源与工程

美国|英语

来源: SciTech Connect

【 摘 要 】

As the nuclear industry moves to advanced ceramic based materials for cladding and core structural materials for a variety of advanced reactors, new standards and test methods are required for material development and licensing purposes. For example, General Atomics (GA) is actively developing silicon carbide (SiC) based composite cladding (SiC-SiC) for its Energy Multiplier Module (EM2), a high efficiency gas cooled fast reactor. Through DOE funding via the advanced reactor concept program, GA developed a new test method for the nominal joint strength of an endplug sealed to advanced ceramic tubes, Fig. 1-1, at ambient and elevated temperatures called the endplug pushout (EPPO) test. This test utilizes widely available universal mechanical testers coupled with clam shell heaters, and specimen size is relatively small, making it a viable post irradiation test method. The culmination of this effort was a draft of an ASTM test standard that will be submitted for approval to the ASTM C28 ceramic committee. Once the standard has been vetted by the ceramics test community, an industry wide standard methodology to test joined tubular ceramic components will be available for the entire nuclear materials community.