Diffusion, Thermal Properties and Chemical Compatibilities of Select MAX Phases with Materials For Advanced Nuclear Systems

Barsoum, Michel¹  Bentzel, Grady¹  Tallman, Darin J.¹  Sindelar, Robert²  Garcia-Diaz, Brenda²  Hoffman, Elizabeth² 

[1] Drexel Univ., Philadelphia, PA (United States);Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

关键词: NEUTRONS;    SILICON CARBIDES;    ALUMINIUM CARBIDES;    SPECIFIC HEAT;    THERMAL CONDUCTIVITY;    TEMPERATURE RANGE 0400-1000 K;    TEMPERATURE RANGE 1000-4000 K;    IRRADIATION;    PYROLYTIC CARBON;    COMPATIBILITY;    FLIBE;    URANIUM;    PALLADIUM;    SODIUM;    LEAD;   

DOI  :  10.2172/1253946
RP-ID  :  DOE/NEUP--11-3231
PID  :  OSTI ID: 1253946
Others  :  Other: 11-3231
Others  :  TRN: US1601397

学科分类：材料科学（综合）

美国|英语

来源: SciTech Connect

【 摘 要 】

The demands of Gen IV nuclear power plants for long service life under neutron irradiation at high temperature are severe. Advanced materials that would withstand high temperatures (up to 1000+ ??C) to high doses in a neutron field would be ideal for reactor internal structures and would add to the long service life and reliability of the reactors. The objective of this work is to investigate the chemical compatibility of select MAX with potential materials that are important for nuclear energy, as well as to measure the thermal transport properties as a function of neutron irradiation. The chemical counterparts chosen for this work are: pyrolytic carbon, SiC, U, Pd, FLiBe, Pb-Bi and Na, the latter 3 in the molten state. The thermal conductivities and heat capacities of non-irradiated MAX phases will be measured.