Simulation of delayed neutrons using MCNP

Abstract Accurate modeling of the delayed neutron response in a fission process has been a desired capability for MCNP TM (Briesmeister, 2000). After a year of data library and code development, a delayed neutron feature has now been incorporated into the latest version of MCNP, 4C. In this work, a validation of the integrated delayed neutron model is performed by comparisons to an analytic solution and experimental results.