作者: Guangming Zhou , Min Li , Qianwen Liu , Shuai Wang , Zhongliang Lv
DOI: 10.1007/S10894-014-9798-Y
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摘要: As one of the candidate tritium breeding blankets for Chinese Fusion Engineering Test Reactor, a kind helium cooled solid breeder blanket was proposed. The uses pebbles lithium ceramics (Li4SiO4) and beryllium as neutron multiplier, respectively. thermal conditions unit directly affect performance safety blanket. Therefore, analysis pebble beds is vital importance reliable design. State steady hydraulic has been performed, showing that temperature satisfied corresponding material limits. thermo-mechanical also carried out. maximum von Mises stress within allowable stress. Parametric sensitivity studies have conducted to investigate influence main parameters (e.g. coolant mass flow rate, inlet bed conductivity) on distribution cooling plates.