Year
2015
Abstract
Neutron multiplicity measurements can be used for safeguards applications like fissile material accountancy as well as for disarmament verification tasks, e.g. identifying nuclear warheads. Simulation of these measurements help to create new detectors and to identify their limitations and weaknesses. Depending on the sample, (a, n)-reactions contribute significantly to the neutron source term. The paper presents a method to derive the rate of these reactions independent of the problem geometry by simulation. The method is embbeded in an application using the Monte Carlo framework Geant4. An interface to use evaluated reac- tion data (e.g. JENDL/AN-2005) has been implemented. Benchmark calculations using the application will be compared to experimental data sets.