Research On Beam-shaping-assembly Of D-T Reaction Neutron Source And Beam Characteristic

The transportation of fast neutron in the shielding material was simulated with MCNP code in this thesis paper. Which have considered the effects of the neutron energy spectrum, angular distribution, source configuration and target materials. After the analysis of flux, energy spectrum of neutron/gamma and its absorbed dose in water that out of the shielding objects, three shielding plans that suitable for the T(d,n)4He fast neutron therapy were obtained. According to the compound shielding plans, the structure optimization design and the shielding properties measurement of projectile beam shielding object for original fast neutron therapy have been carried out.The performances of the collimated fast neutron projectile beam were simulated and analysed. Which included the beam flux,energy spectrum, the deep-dose distribution and its transversal deep-dose distribution in different depth of neutron/gamma in equivalent water, the neutron absorption dosage half-shadow, and the uniformity of the radiation field etc.The simulation result of each performance of optimizing shielding shows that, the D-T fast neutron therapy is achievable. And the measurement results of absorbed dose distribution, absorbed dose rate, and deposited dose within 15cm penetration range may satisfy the clinical application.