EPJ Web of Conferences
Volume 106, 2016ISRD 15 – International Symposium on Reactor Dosimetry
|Number of page(s)||8|
|Section||Transport Calculations (Neutron and Gamma-Ray) and Modeling|
|Published online||03 February 2016|
Application of the Subgroup Decomposition Method (SDM) for Reactor Simulation
Nuclear Engineering Program, Mechanical Engineering Department, Virginia Tech, Arlington, VA, USA
Published online: 3 February 2016
The performance of the TITAN-SDM algorithm for solving a reactor pressure vessel dosimetry problem is evaluated. Douglass and Rahnema recently developed the he subgroup decomposition method (SDM); a methodology which directly couples a consistent coarse-group transport calculation with a set of “decomposition sweeps” to provide a fine-group flux spectrum. The SDM has been implemented into the TITAN three-dimensional transport code and has been shown to accurately solve core criticality problems while significantly reducing computation time. This paper addresses the use of SDM for fixed-source problems. The VENUS-2 dosimetry benchmark problem is selected with an emphasis on fast neutron analysis; therefore, material cross sections are generated from the BUGLE-96 library considering neutron energies greater than 0.1 MeV. The accuracy and efficiency of TITAN-SDM is evaluated by comparison with a standard TITAN multigroup calculation.
© Owned by the authors, published by EDP Sciences, 2016
This is an Open Access article distributed under the terms of the Creative Commons Attribution License 2.0, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
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