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Simulation of delayed neutrons using MCNP
Authors:Christopher J. Werner
Affiliation:

Los Alamos National Laboratory, MS F663, Los Alamos, NM 87545-001, USA

Abstract:Accurate modeling of the delayed neutron response in a fission process has been a desired capability for MCNPTM (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.
Keywords:
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