Abstract
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.
Highlights
Douglass and Rhanema developed a novel method for performing multigroup transport calculations for core physics application, i.e. core criticality calculation
The VENUS-2 dosimetry benchmark problem is selected with an emphasis on fast neutron analysis; material cross sections are generated from the BUGLE-96 library considering neutron energies greater than 0.1 MeV
TITAN-subgroup decomposition method (SDM) is sensitive to the number of coarse-groups selected and the definition of the coarse-group boundaries
Summary
Douglass and Rhanema developed a novel method for performing multigroup transport calculations for core physics application, i.e. core criticality calculation. This method, referred to as Subgroup Decomposition Method (SDM) [1], is an extension of the standard cross-section condensation process [2] that preserves spectral accuracy as well as the energy-angle coupling which is generally lost in standard condensed-group transport calculations. TITAN-SDM has been previously demonstrated for core criticality calculations on both a one- and two-dimensional Very High Temperature Reactor (VHTR) core model [4]. The results demonstrated that, for a core criticality problem, the SDM algorithm is capable of significantly reducing computation time while maintaining adequate accuracy in both the eigenvalue and flux distribution
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