Building on the work described in our previous posts (please see links below), we have continued developing NEUTRO, the neutronics module in Alya. The latest advancements are portrayed in the article entitled “Validating NEUTRO, a deterministic finite element neutron transport solver for fusion applications, with literature tests, experimental benchmarks and other neutronic codes” that has been recently published in Plasma Physics and Controlled Fusion (PPCF).
Neutron damage to fusion reactor materials and tritium self-sufficiency are two significant challenges that need to be solved for fusion to be a viable energy source integrated with the electricity grid. The development of future fusion reactors requires a thorough understanding and the ability to predict these processes, which in turn means highly demanding simulations need to be performed to assist in the analysis of the consequences of neutrons interacting with the vast array of reactor components.
