Investigation on the Possibility of Tritium Self-Sufficiency for CFETR Using a PWR Water-Cooled Blanket

IEEE Transactions on Plasma Science(2014)

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摘要
The neutron wall load (Pn) of Chinese fusion engineering testing reactor (CFETR) will be less than 1 MW/m2. To meet the net tritium breeding ratio (TBR) of the reactor, a new water-cooled blanket concept is considered. The blanket neutronics schemes are performed to explore the local TBR issues in the (Pn) range of 1-5 MW/m2, which aims at the effective design of the blanket concept considering th...
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关键词
Cooling,Inductors,Materials,Fusion reactors,Heating,Educational institutions,Plasmas
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