Although the neutron mean free path in typical fast reactors is long compared with that of typical thermal reactors, the heterogeneous flux distributions in angular domain and spatial domain are notable due to the strong elastic-scattering resonance and common core-level heterogeneous layout. Full-core multigroup transport analysis becomes inevitable for advanced fast reactor R&D. A fast reactor neutronics analysis system, SARAX is under development at XJTU of China. An existing in-house SN-nodal solver in triangular-Z geometry, DNTR was primarily chosen for its geometric adaptability. However, insufferable problems of computing time and storage were encountered when the solver was on active service. In this paper, the problems are firstly analysed and resolved from the theory and code levels. Then, widely used CMFD acceleration method with some stabilization techniques is implemented for the SN-nodal method in triangular-Z geometry, which can largely reduce the computing time. What’s more, a new acceleration method TCD is proposed and can obtain superior speedups with reasonable accuracy sacrifice. The updated solver, DNTR 1.1 has been developed based on these improvements, which can obtain dozens of speedup with reduced storage compared with DNTR for typical fast reactor simulation on a desktop computer.

This content is only available via PDF.
You do not currently have access to this content.