Computer simulations of the moderator structure for 14MeV neutron source have been made by using TAMAKER- ANISN Program and 46 groups (25 neutron groups and 21 Photon groups) UW cross-section data with an IBM/PC AT computer.Polythene was chosen as the moderation material and lead as the intensifying msterial. In the calculation the (n
2n) reaction of lead was acted as a fission source introduced into the source term of the transport equation. The calculation results have been justified by the experiments and the optimum structural combination ofpolythene and lead has been found. In principle
the intensifying factor for the peak thermal neutron may be larger than 3.0 when using lead as the intensifying material in polyethene moderator.