A neutronic benchmark specification and COMET solution for the Advanced Burner Test Reactor

Using this benchmark and 15 group cross sections, the Coarse Mesh Transport Method (COMET) code was verified against the Monte Carlo code MCNP. Results were generated for three separate core cases: control rods out, near critical, and control rods in. Eigenvalue comparison results between COMET and MCNP are within 50 pcm for all three cases, well within two standard deviations of the stochastic uncertainty of the solution methods. The fission density results are highly accurate with a pin fission density average discrepancy between COMET and MCNP of less than 0.5% for each model.