Analyses of radiation fields resulting from a deuterium-tritium (DT) plasma in fusion devices is a critical input to the design and validation of many aspects of the reactor design, such as shielding, material lifetime and remote maintenance requirements/scheduling. Neutronics studies are performed using radiation transport codes such as MCNP, TRIP…
Nuclear analysis supporting the design and licensing of ITER is traditionally performed using MCNP and the reference model ‘C-Model’, however the complexity of C-Model has resulted in the geometry creation and integration process becoming increasingly time-consuming. Serpent 2 is still a beta code, however recent enhancements mean that it could…
