MCODE, Version 2.2: An MCNP-ORIGEN DEpletion Program

MCODE, Version 2.2: An MCNP-ORIGEN DEpletion Program

MCODE Version 2.2 is a linkage program, which combines the continuous-energy Monte Carlo code, MCNP-4C, and the one-group depletion code, ORIGEN2, to perform burnup calculations for nuclear fission reactor systems. MCNP is used as the advanced physics modeling tool providing the neutron flux solu...

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Bibliographic Details
Main Authors: Xu, Z., Hejzlar, Pavel
Other Authors: Massachusetts Institute of Technology. Nuclear Fuel Cycle Program
Format: Technical Report
Published: Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program 2012
Online Access:http://hdl.handle.net/1721.1/75242

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