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3 Application to the evaluation of heat flow in nuclear reactor systems
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3.2 Thermal Feasibility of water reactor for Flexible Fuel Cycle (FLWR)
Research contents
3.2 Thermal Feasibility of water reactor for Flexible Fuel Cycle (FLWR)
3.2.1 37-rod bundles test
3.2.2 Experimantal estimation for the Effect of Axial Power Distribution on Critical Power