مدخل إلى برنامج محاكاة انتقال الإشعاعات النووية MCNP

Abstract

Abstract:

This research paper gives a brief overview with regard to utilizing MCNP coding software which is an important program in the field of radiometric instrumentation and modelling. This type of software is based on Monte Carlo calculation method so as to have the ability to simulate process a full simulation to nuclear radiations from a simple project such as a point isotopic source with a cylindrical radiation detector to a project as complicated as a lung tissue stopping power for a modified phantom or even full simulation to a nuclear reactor.