Dosimetry calculations based on MCNP code of the Training Reactor of Budapest University of Technology and Economics

This study presents the work of Vietnamese experts performed during a twelve-week training at BME. The MCNP code was used to model the BME Training Reactor. Dose rates were determined for neutrons and photons for the top of the reactor, the outer of the concrete wall as well as the inside of the vertical water irradiation channels and the pneumatic rabbit system at different power levels and in case of the loss of water. Calculated data are in good agreement with the measured values.

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