Abstract
An assessment of the neutron field near VENUS reactor is made in order to evaluate the neutron dose in an area near the reactor shielding and in the control room. Therefore, a full MCNPX model of the shielding geometry was developed. The source term in the simulation from a critical calculation done beforehand. Calculations are compared to routine neutron dose rate measurements and show good agreements. The MCNPX model developed easily allows core adaptations in orde to evaluate the effect of futur core configuration on the neutron dose to the operator.
Original language | English |
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Pages (from-to) | 76-79 |
Journal | Radiation protection dosimetry |
Volume | 115 |
Issue number | 1-4 |
DOIs | |
State | Published - 12 Nov 2005 |