Below are examples of work that the NRCC group has done in the past.

Flux and dose estimates were generated with MCNPX on a large building facility at the Nevada Test Site. The large Dense Plasma Focus device (yield of 1 x 10¹²  neutrons per shot with D-D) was being moved to the A-1 building and dose estimates to the nearby workers were calculated. Large scale simulations require variance reduction (such as weight window generation and DXTRAN spheres) to allow the tallies to converge while the use of many computers allow the statistical errors in those tallies to go down.

Neutron flux predictions were obtained through MCNPX simulations in support of the Advanced Accelerator Applications (currently the
Advanced Fuels Cycle Initiative). A lead-bismuth slug was irradiated at the 800 MeV proton accelerator at LANSCE in Los Alamos. Neutron
fluxes and benchmarking studies were obtained from this experiment in 2002.

Radiation transport studies were performed on the Nevada Test Site's Dense Plasma Focus machine to tailor a mono-energetic neutron
source to a fission spectrum. Distance, shielding material, shielding configuration, and reflector shape were varied to obtain this goal. 

Neutron and photon flux calculations were performed using MCNPX for Sandia's ZR machine that is slated to be built in late 2007. MCNPX was used to optimize the shielding pig that will be used to house sensitive neutron detectors built by the Nevada Test Site. The goal of the project was to maximize the uncollided neutron flux at the detectors while trying to minimize the collided neutron and photon flux. 

Dose estimates were calculated with MCNPX for the cargo inside trailers that are subject to x-ray scanners. Cargo scanning at the U.S. ports has risen since 9/11 and homeland security officials are concerned that illegal immigrants that may be housed in these trailers will be exposed to a large radiative dose. The goal of this project is to determine the maximum dose a human can be exposed to in this scenario.