MCNP5 DELAYED NEUTRON FRACTION &beta _eff CALCULATION IN TRAINING REACTOR VR-1

Svetozár Michálek - Ján Haščík - Gabriel Farkas

   In this paper, possible determination methods of one main parameters of the reactor dynamics - the effective delayed neutron fraction &beta _eff are summarized and a calculation is made for VR-1 training reactor using the stochastic transport Monte Carlo method based code MCNP5.

Keywords: delayed neutron fraction &beta _eff reactor dynamics, MCNP transport code, nuclear reactor

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