Graphical User Interface for Simplified Neutron Transport Calculations

With the increased importance in performing neutron calculations for homeland security applications and defense nuclear nonproliferation tasks, it becomes increasingly important to have an efficient method for performing simple neutron transport calculations. Codes such as the Monte Carlo N-particle (MCNP) exist that can perform the transport calculations; however, the technical details in setting up, running, and interpreting the required simulations are quite complex and typically go beyond the abilities of most users. This project will develop a software program that can create an MCNP input file and is constrained to a number of simple geometries, source, and detector configurations. The goal is to create a simplified user interface that will allow a user to specify a simple geometry configuration, select from specific source geometries, and then specify detector types and locations. Commercial Applications and other Benefits as described by the awardee A simplified neutron transport tool would benefit include the DOE Office of Nonproliferation Research and Development, the Department of Homeland Security, the Domestic Nuclear Detection Office, and the Defense Threat Reduction Agency. A large demand for this tool is anticipated, as no such capability now exists. Similar programs that perform only photon calculations currently sell for approximately $2,000 a copy