Steady-State Thermal-Hydraulic Analysis of the LEU-Fueled Dalat Nuclear Research Reactor

<div>Comparison of the measured cladding temperatures (T<sub>1</sub> ÷ T<sub>5</sub>) and coolant temperatures (T<sub>in</sub>, T<sub>out</sub>) of the HEU core to calculated those of the LEU core using the PLTEMP/ANL code.</div>

Science and Technology of Nuclear Installations

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Figure 5

Figure 5: Steady-State Thermal-Hydraulic Analysis of the LEU-Fueled Dalat Nuclear Research Reactor 