This page is the beginning of a hands-on tutorial in Serpent that will walk you through the creation of simple pin-cell and assembly geometry models and the use of those models for some reactor physics simulations.
Compiled version of Serpent 2
Explain different (typical) parts such as:
Input for 2D pin-cell geometry
% --- Simple 2D PWR pin-cell geometry for Serpent tutorial /************************ * Material definitions * ************************/ % --- Fuel material (3.0 wt-% enriched uranium dioxide), density 10.1 g/cm3 mat fuel -10.1 92235.03c -0.02644492 92238.03c -0.85505247 8016.03c -0.11850261 % --- Cladding material for fuel rod % (100 % Zirconium) mat clad -6.55 40000.03c -1.0 % --- Water at 1.0 g/cm3 mat water -1.0 1001.03c 2.0 8016.03c 1.0 /************************ * Geometry definitions * ************************/ % --- Fuel pin structure pin p1 fuel 0.4025 clad 0.4750 water % --- Square surface with 1.0 cm side centered at (x,y) = (0,0) surf s1 sqc 0.0 0.0 0.5 cell c1 0 fill p1 -s1 cell c2 0 outside s1 /****************** * Run parameters * ******************/ % --- Neutron population set pop 5000 100 20 % --- Boundary condition (1 = black, 2 = reflective, 3 = periodic) set bc 2 % --- Geometry plots plot 3 200 200 plot 3 1000 1000 0.0 -2.5 2.5 -2.5 2.5 % --- Cross section library file set acelib "xsdir0K"
