Oxidation Resistant Graphite Studies

W. Windes ; R. Smith

关键词: FUELS;    GRAPHITE;    OXIDATION AGR;    Fuels;    Graphite;    HTR;    NGNP;    Oxidation;    SiC;    TDO;    VHTR;   

DOI  :  10.2172/1164863
RP-ID  :  INL/EXT-14-32513
PID  :  OSTI ID: 1164863

学科分类：核能源与工程

美国|英语

来源: SciTech Connect

【 摘 要 】

The Very High Temperature Reactor (VHTR) Graphite Research and Development Program is investigating doped nuclear graphite grades exhibiting oxidation resistance. During a oxygen ingress accident the oxidation rates of the high temperature graphite core region would be extremely high resulting in significant structural damage to the core. Reducing the oxidation rate of the graphite core material would reduce the structural effects and keep the core integrity intact during any air-ingress accident. Oxidation testing of graphite doped with oxidation resistant material is being conducted to determine the extent of oxidation rate reduction. Nuclear grade graphite doped with varying levels of Boron-Carbide (B4C) was oxidized in air at nominal 740?��C at 10/90% (air/He) and 100% air. The oxidation rates of the boronated and unboronated graphite grade were compared. With increasing boron-carbide content (up to 6 vol%) the oxidation rate was observed to have a 20 fold reduction from unboronated graphite. Visual inspection and uniformity of oxidation across the surface of the specimens were conducted. Future work to determine the remaining mechanical strength as well as graphite grades with SiC doped material are discussed.