MCNP model of photoneutron source has been developed. The leakage neutron spectrum from the beryllium target of thickness 2 cm and 9 cm diameter is estimated by Monte Carlo calculation using MCNP code. The NCRP-38 flux to dose conversion factors has been used for neutron dose calculation. The calculated neutron dose at 42 cm from the source is 5.29E-04 ± 5.9% Sv/h. The experimentally measured neutron dose using the Neutron rem detector is 5.52E-04 ± 3.9% Sv/h.