Development of a New Fixed-source Sensitivity Tally Capability in the MCNP® Code [Slides]

Abstract

The development of a new fixed-source sensitivity tally capability, targeted toward nuclear data parameters, is currently underway in the MCNP code. In recent research and development efforts that utilize machine learning to both seek problematic nuclear data as well as design experiments optimized to improve the nuclear data, the adjoint-weighted k-eigenvalue sensitivity tally capabilities have been essential. In this paper, the motivation to expand the sensitivity tally capabilities beyond k-eigenvalues toward diverse fixed-source problems along with preliminary results and verification will be discussed.