Year
2015
Abstract
Recent interest in modeling and simulation of detector systems has led to several enhancements to the radiation transport code, MCNP6. The most recent improvement to the detector modeling capability has been the expansion of the built- in detector response functions. MCNP first implemented dose functions in MCNPX 2.4.0 and since then specific detector types have been added. The next release of MCNP6 will include response functions for 5 new neutron detector types along with the previously built-in photon detector responses. This paper will demonstrate the use of the new response functions as well as provide benchmarking.