수소/붕소 혼합체에 대한 고속중성자 차폐 특성 분석

Abstract

In this research to find out the optimum composition ratio of hydrogen and boron in those mixture materials for neutron shielding, MCNP code calculation is carried out. Isotropic point source of mono energetic 14.1 MeV neutron located at 100cm in front of target is irradiated to postulated H and B mixture materials which thickness is 16 cm. The fact that hydrogen atom can moderate the high energetic neutron effectively and boron is a appropriate nuclide for absorption of thermal neutron is confirmed. More intensive study to optimize the mixture ratio will be carried out using subdivided energy bin in the sensitive energy for cross section.