Development of new cladding types for nuclear fuel

被引：2

作者：

Hozer, Z. ^{[1
]}

Novotny, T. ^{[1
]}

Perez-Fero, E. ^{[1
]}

Horvath, M. ^{[1
]}

Csordas, A. Pinter ^{[1
]}

Szabo, P. ^{[1
]}

Illes, L. ^{[1
]}

Schyns, M. ^{[2
]}

Delville, R. ^{[2
]}

Kim, D. ^{[3
]}

Kim, W. J. ^{[3
]}

Sevecek, M. ^{[4
]}

机构：

[1] Ctr Energy Res, Budapest, Hungary

[2] SCK CEN Belgian Nucl Res Ctr, Mol, Belgium

[3] Korea Atom Energy Res Inst, Daejeon, South Korea

[4] Czech Tech Univ, Prague, Czech Republic

来源：

12TH HUNGARIAN CONFERENCE ON MATERIALS SCIENCE (HMSC12) | 2020年 / 903卷

关键词：

HIGH-TEMPERATURE OXIDATION; E110; ZIRCALOY-4;

D O I：

10.1088/1757-899X/903/1/012004

中图分类号：

O646 [电化学、电解、磁化学];

学科分类号：

081704 ;

摘要：

Three different cladding types were tested for nuclear fuel in traditional light water reactors and generation IV gas-cooled fast reactors. Cr coated Zr cladding was tested in steam atmosphere up to 1200 degrees C to demonstrate moderate oxidation and hydrogen production in accident conditions. 15-15Ti stainless steel alloy and SiCf/SiC cladding tube samples were treated in helium atmosphere with different impurities for several hours at 1000 degrees C. Additional mechanical testing and microstructure examinations were carried out with as-received samples and with specimens after high temperature treatments. The experiments results indicated the applicability of the tested materials for reactor conditions in the investigated range of parameters.

引用

页数：8

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