TEM Examination of Advanced Alloys Irradiated in ATR

Jian Gan, PhD

关键词: ALLOYS;    BURNERS;    FAST NEUTRONS;    INCOLOY 800H;    IRRADIATION;    MARTENSITIC STEELS;    NUCLEAR ENERGY;    NUCLEAR POWER;    OXIDES;    PERFORMANCE Advanced Alloys Irradiated;    ATR;    TEM Exam;   

DOI  :  10.2172/933193
RP-ID  :  INL/EXT-07-13306
PID  :  OSTI ID: 933193
Others  :  TRN: US0803788

学科分类：核能源与工程

美国|英语

来源: SciTech Connect

【 摘 要 】

Successful development of materials is critical to the deployment of advanced nuclear power systems. Irradiation studies of candidate materials play a vital role for better understanding materials performance under various irradiation environments of advanced system designs. In many cases, new classes of materials have to be investigated to meet the requirements of these advanced systems. For applications in the temperature range of 500 800ÂşC which is relevant to the fast neutron spectrum burner reactors for the Global Nuclear Energy Partnership (GNEP) program, oxide dispersion strengthened (ODS) and ferritic martensitic steels (e.g., MA957 and others) are candidates for advanced cladding materials. In the low temperature regions of the core (<600ÂşC), alloy 800H, HCM12A (also called T 122) and HT 9 have been considered.