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Preliminary Neutronics Analysis for a Compact Heat-Pipe Cooled Fast Reactor Core
Preliminary Neutronics Analysis for a Compact Heat-Pipe Cooled Fast Reactor Core
2019
Qin Zeng
Yao Zhou
Ying Shi
Chenghao Li
Putong Wang
Keywords:
Heat pipe
Neutron transport
Nuclear reactor core
Nuclear engineering
Materials science
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