Graphical User Interface for Simplified Neutron Transport Calculations

Schwarz, Randolph ; Carter, Leland L

关键词: Shielding Neutron Transport;   

DOI  :  10.2172/1018953
RP-ID  :  DOE/SC0002321-1
PID  :  OSTI ID: 1018953

美国|英语

来源: SciTech Connect

【 摘 要 】

A number of codes perform simple photon physics calculations. The nuclear industry is lacking in similar tools to perform simplified neutron physics shielding calculations. With the increased importance of performing neutron calculations for homeland security applications and defense nuclear nonproliferation tasks, having an efficient method for performing simple neutron transport calculations becomes increasingly important. Codes such as Monte Carlo N-particle (MCNP) 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 who need a simple answer to a neutron transport calculation. The work documented in this report resulted in the development of the NucWiz program, which can create an MCNP input file for a set of simple geometries, source, and detector configurations. The user selects source, shield, and tally configurations from a set of pre-defined lists, and the software creates a complete MCNP input file that can be optionally run and the results viewed inside NucWiz.