Simulation Of Pulsed Neutron Source Reactivity Measurements And Calculation Of Kinetic Parameters With Mcnp

摘要

Reactivity determination is the most important measurement conducted on reactors. The reason is the key role of reactivity in the description of reactor behavior. A widely used reactivity determination method is a pulsed neutron source (PNS) measurement. For many research reactors with nonstandard reactor geometry, the only suitable method of solution for the neutron transport equation is the Monte-Carlo method which is used in the popular MCNP code. A new method of calculating the effective delayed neutron fraction (β_(eff)) has been developed for simulation of accelerator-driven subcritical system (ADS) experiments in the Reactor-Accelerator Coupling Experiments (RACE) Project at the Idaho State University Idaho Accelerator Center (ISU IAC), which were conducted in August and October of 2006.