Study on Source Terms in Station Blackout Accident of Qinshan-ⅠNuclear Power Plant
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Graphical Abstract
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Abstract
The behaviors including release, transport and final distribution of different kinds of radioactive fission products were analyzed by using MELCOR code for Qinshan-Ⅰnuclear power plant in the case of an accident sequence of station blackout. The source terms released into environment, which are necessary for the assessment of the accident consequences, were also calculated.
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