To further enhance HTGR safety, we are developing the oxidation-resistant fuel, which can maintain its integrity even if a much larger amount of air enters than expected in an air ingress accident by pipe rupture of primary cooling system. The oxidation resistance is improved by employing SiC/C mixed matrix for fuel compacts. The nuclear thermal design of HTGR and fuel design with the matrix were performed, and the feasibility is confirmed. Experiment to confirm the manufacturability was also performed.
Photographs of side and top surfaces of oxidation-resistant fuel elements (dummy fuel)
- Reference
- Y. Tachibana, "Research on innovative fuel element to enhance safety of HTGR,"
H28 eichi wo kessyuushita genshiryokukagakugijyutu
jinnzaiikuseisuishinjigyouhoukokukaisiryou,(2016) [in Japanese]- J. Aihara, M. Goto, Y. Inaba, "Nuclear thermal design of high temperature gas-cooled reactor with SiC/C mixed matrix fuel compacts," HTR 2016, (2016).