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Principal Research Results Development of multi-COBRA: A Transient Thermal-hydraulic Analysis Code for Fast Reactor Cores Background In liquid-metal-cooled fast reactors (LMFRs), the coolant flow coastdown events due to
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Document Date: 2008-09-29 03:25:43
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Principal Research Results Development of multi-COBRA: A Transient Thermal-hydraulic Analysis Code for Fast Reactor Cores Background In liquid-metal-cooled fast reactors (LMFRs), the coolant flow coastdown events due to