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In the present research, sub-channel thermal-hydraulic analysis of the Bushehr Nuclear Power Plant (BNPP) core, a Russian VVER-1000 type, at hot full power (HFP) and steady state BOC conditions is presented herein using modified COBRA-EN code. Required power distribution and hot channel factors were computed by our past neutronics calculations using MCNP-5 code. Due to increasing temperature, modification...
A global, system-level thermal-hydraulic model of the EU DEMO tokamak fusion reactor is currently under development and implementation in a suitable software at Politecnico di Torino, including the relevant heat transfer and fluid dynamics phenomena, which affect the performance of the different cooling circuits and components and their integration in a consistent design. The model is based on an...
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