Creep of Structural Nuclear Composites

Windes, Will ; Lloyd, R.W.

Idaho National Laboratory

关键词: Research Programs;    Tensile Properties;    Control Elements;    36 - Materials Science;    Irradiation;   

DOI  :  10.2172/911783
RP-ID  :  INL/EXT-05-00747
RP-ID  :  DE-AC07-99ID-13727
RP-ID  :  911783

美国|英语

来源: UNT Digital Library

【 摘 要 】

A research program has been established to investigate fiber reinforced ceramic composites to be used as control rod components within a Very High Temperature Reactor (VHTR) design. Two candidate systems have been identified, carbon fiber reinforced carbon (Cf/C) and silicon carbide fiber reinforced silicon carbide (SiCf/SiC) composites. One of the primary degradation mechanisms anticipated for these core components is high temperature thermal and irradiation enhanced creep. As a consequence, high temperature test equipment, testing methodologies, and test samples for very high temperature (up to 1600º C) tensile strength and long duration creep studies have been established. Actual testing of both tubular and flat, "dog-bone"-shaped tensile composite specimens will begin next year. Since there is no precedence for using ceramic composites within a nuclear reactor, ASTM standard test procedures are currently being established from these high temperature mechanical tests.