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A thermodynamic approach for advanced fuels of gas-cooled reactors

机译:气冷反应堆高级燃料的热力学方法

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For both high temperature reactor (HTR) and gas cooled fast reactor (GFR) systems, the high operating temperature in normal and accidental conditions necessitates the assessment of the thermodynamic data and associated phase diagrams for the complex system constituted of the fuel kernel, the inert materials and the fission products. A classical CALPHAD approach, coupling experiments and thermodynamic calculations, is proposed. Some examples,of studies are presented leading with the CO and CO2 gas formation during the chemical interaction of [UO2 +/- x/C] in the HTR particle, and the chemical compatibility of the couples [UN/SiC], [(U, Pu)N/SiC], [(U, Pu)N/TiN] for the GFR system. A project of constitution of a thermodynamic database for advanced fuels of gas-cooled reactors is proposed. (c) 2005 Elsevier B.V. All rights reserved.
机译:对于高温反应堆(HTR)和气冷快堆(GFR)系统,正常和意外情况下的高工作温度都需要评估由燃料核组成的复杂系统的热力学数据和相关的相图。材料和裂变产物。提出了一种经典的CALPHAD方法,耦合实验和热力学计算。提出了一些研究实例,这些研究导致了HTR颗粒中[UO2 +/- x / C]的化学相互作用期间CO和CO2气体的形成,以及[UN / SiC]对的化学相容性,[(U ,Pu)N / SiC],[(U,Pu)N / TiN]用于GFR系统。提出了气冷反应堆高级燃料热力学数据库的构建项目。 (c)2005 Elsevier B.V.保留所有权利。

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