Neutronics and thermal-hydraulics coupling analysis for a small lead-based fast reactor based on the discrete ordinate nodal and parallel channel method

The full-core neutronics/thermal-hydraulics (NE/TH) coupling analysis for a small lead-based fast reactor (SLFR) was presented. NE-to-TH occurs via power distribution, whereas the TH-to-NE material cross section, which is related to temperature distribution. In NE module, discrete ordinate (SN) nodal solver implemented based on hexagonal prism mesh. TH parallel channel model with each fuel assembly as channel. mass flow of searched according same pressure drop, and density coolant within calculated one-dimensional axial heat convection model, distribution along pin radial conduction model. order update temperature-dependent homogenized microscopic cross-section library prepared in advance, obtained from calculation, data required by calculation are interpolation. results NE/TH SLFR indicate that parameters (the maximum fuel, cladding, velocity coolant) all design limits, feedback provides negative reactivity (about −200 pcm) has fairly effect (<1.0%).