Metz Peter | International Cooperation And Technology Development Center Japan Nuclear Cycle Development Institut
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International Cooperation And Technology Development Center Japan Nuclear Cycle Development Institut | 論文
- Estimation of FBR MONJU's Average Fuel Temperatures and Fuel-to-coolant Heat Transfer Coefficients using Trip-Test Data
- Validation of the MSG (Multi-dimensional Thermal-hydraulics Analysis Analysis Code for Steam Generators) for CFD Modelling of Sodium Heated Steam Generators