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, in principle, be applied to ITER neutronics analysis. Investigations have been undertaken into the effectiveness of Serpent for ITER neutronics analysis and whether this might offer an efficient modelling environment. An automated MCNP to Serpent model conversion tool was developed, and successfully used to create a Serpent 2 variant of C-Model. A version of the D-T plasma neutron source was also created. Standard reference tallies in C-Model for the blanket and vacuum vessel heating were implemented and comparisons made between the two transport codes assessing nuclear responses and compute requirements in the ITER model. Excellent agreement was found between the two codes when comparing neutron and photon flux and heating in the ITER blanket modules and vacuum vessel. Comparing tally figures of merit, compute requirements for Serpent were typically 3-5 times that of MCNP, and memory requirements broadly similar. Whilst slower than MCNP when applied to fusion neutronics, future developments may improve this, and the code offers clear benefits which will reduce analyst time, including: support for meshed geometry; a robust universe implementation which avoids geometry errors at the boundaries, and mixed geometry types. Additional work is proceeding to compare Serpent against experiment benchmarks relevant for fusion shielding problems. Whilst further developments are needed to improve variance reduction techniques and reduce simulation times, this paper demonstrates the suitability of Serpent to some aspects of ITER analysis.