Modeling Transportation Risk for Spent Nuclear Fuel

Spent nuclear fuel (SNF) transportation is a critical aspect of nuclear energy infrastructure. This paper introduces a Monte Carlo-based computational approach to assess the risk associated with SNF transportation, including low-probability, high-consequence events. The SNF Transportation Risk (SNFTR) code developed is presented; furthermore, this paper outlines its foundational assumptions. The SNFTR code provides a concise visualization of simulation results, offering a risk assessment and a risk communication tool. The SNFTR code empowers local communities to autonomously evaluate transportation risks in the current nuclear power system, essential as the U.S. federal government advances plans for SNF storage. This computational modeling approach enhances transparency and technical understanding, facilitating informed decision-making and fostering confidence in SNF trans-portation safety.