Simulation: Neutron transport simulation constultancy

Adelphi would be happy to be a consultant for your neutron transport calculations and simulation needs. This may prove cost-effecive route to simulation, not because of the expense of the software, but because the software has a long learning curve. It has a very long history and it shows signs of its age - dating back to the punch-card era of computing. MCNP consultancy involves getting a clear understanding of your needs, preparing a preliminary design to be simulated. The results from the simulation typically inform modifications such as a change in the choice of materials or changes in the physical design (thicknesses of materials). The process may be iterated a few times until, practical design is determined.

We typically use mcnp for neutron transport simulations. However, we do also use open source software GEANT4. There is an open source neutron transport code called OpenMC which could also be used for neutron transport simulation.

We would be happy to discuss simulation consultancy .

Example: Simulation of Beam Shaping Aparatus

We have used mcnp simulation in the design of a Beam Shaping Aparatus (BSA) which we developed to increase the thermal neutron flux from the generator at a sample. This work is described in US Patent US11090509B1.

Example: MCNP simulation of proposed neutron densitometer

Mcnp was used to simulate the neutron field around a proposed neutron densitometer system that was developed to measure the density of materials that were passed through a 'measurement tunnel'. The neutron dose rates surrounding the system were calculated to determine if extra signage and the use of exclusion zones would be needed for operaters who would be placing the objects to be scanned on carts that would pass cylindrical objects through the densitometer.

The Images show the system, and simulated neutron distribition. The "football" sized objects shown in the picture were not real objects, they were imaginary volumes that we used to determine the radiation dose that would be received at various positions from the open neutron densitometer's measurement 'tunnel'.