Advancements in computational methods for neutron shielding

Abstract The radiation transport evaluation using computational methods are essential step for the design and development of nuclear facilities and systems. It is also important to develop new materials as well as conduct experiments on a laboratory scale for the testing of components and materials. The computational modeling of nuclear facilities and experiments provide realistic predictions of the performance and safety, which helps in the improvization and optimization of important relevant parameters. This results in the reduction of safety margins and cost involved in the development of the nuclear facilities. There are basically two methods to simulate the radiation transport in materials which are based on Monte Carlo numerical method and Boltzmann transport-based deterministic method. In the current scenario, there are many commercial as well as open-source software to solve the realistic and more complex geometry problems for the design of nuclear systems as well as for experiments. The popular software available worldwide for the simulations of radiation transport are MCNP, ATTILA, TRIPOLI, SUPER-MC, TORT, etc. A description of the advance simulation codes for the modeling of the radiation transport phenomena to study the radiation interaction and shielding are provided here.