FINIX PB2 CE example input
Revision as of 13:28, 29 November 2017 by Antti Rintala (talk | contribs)
Note: FINIX currently does not include models for many burnup related changes in the fuel rods. The fuel behavior solution will be for fresh fuel at all burnups.
Example of coupled burnup calculations using FINIX. The depletion scheme used is explicit Euler's method with stochastic approximation based relaxation applied to the transmutation cross sections and one-group fluxes used for the depletion solution.
The input model is based on the Peach Bottom 2 BWR assembly from the UAM benchmark [1] with the segmented absorber rod replaced by a full length one. For simplicity the Serpent input has been divided into multiple files using the include card.
Contents
Main Serpent input
% --- Asymmetric BWR assembly with Gd-pins ------------------- set title "Peach Bottom 2 from UAM, FINIX calculation" % --- Remember to set TMS limits for materials include materials include pins include geometry include volumes % --- Reflective boundary condition in XY, black in Z: set bc 2 2 1 % --- Link FINIX input files set finrodfile "./finixfiles/rod_library.txt" set finoptionsfile "./finixfiles/options_library.txt" set finscenariofile "./finixfiles/scenario_library.txt" % --- Define sub-pin-level power binning for FINIX % Name bin1, 6 radial zones in pellet, 10 axial zones finbin bin1 0.0 0.60579 6 -182.88 182.88 10 % --- Link finix solvers for each pin type finrod 1 rod_pb2_nogd options_pb2_all scenario_pb2_all bin1 finrod 2 rod_pb2_nogd options_pb2_all scenario_pb2_all bin1 finrod 3 rod_pb2_nogd options_pb2_all scenario_pb2_all bin1 finrod 4 rod_pb2_nogd options_pb2_all scenario_pb2_all bin1 finrod 5 rod_pb2_yesgd options_pb2_all scenario_pb2_all bin1 % --- Neutron population and criticality cycles: % --- This is simulated on each iteration % !!! This small number does not lead to proper statistics set pop 5000 50 100 % --- This is the number of iterations for each neutronics solution set ccmaxiter 2 % --- Use a smaller number of inactive cycles on subsequent neutron transport solutions % --- (Fission source passing on, number of alternative cycles is 50) set fsp 1 50 % --- Depletion scheme (constant extrapolation, i.e., Explicit euler) set pcc ce % --- Depletion history (just two steps) dep daystep 5 5 % --- Use a lower optimization mode to save memory % Calculations that use the TMS on-the-fly Doppler treatment % do not use grid thinning, which increases memory consumption set opti 1 % --- Division of materials to depletion zones div fuel1 sep 0 subz 10 -182.88 182.88 div fuel2 sep 0 subz 10 -182.88 182.88 div fuel3 sep 0 subz 10 -182.88 182.88 div fuel4 sep 0 subz 10 -182.88 182.88 div fuel5 sep 0 subz 10 -182.88 182.88 subr 5 0.0 0.60579 % --- Total power set power 3.0e+06 % --- Geometry and mesh plots: plot 3 1000 1000 0.0 plot 3 1000 1000 0.0 -22.86 7.62 -22.86 7.62 plot 2 500 1500 plot 1 500 1500 % --- xy-plot of fission power / thermal flux mesh 3 1000 1000 0 -7.62 7.62 -7.62 7.62 -250.0 250.0 % --- xz-plot of fission power / thermal flux mesh 2 1000 3000 0 -7.62 7.62 -7.62 7.62 -250.0 250.0 % --- xy-plot of temperature distribution / thermal flux mesh 10 3 1000 1000 0 -7.62 7.62 -7.62 7.62 -250.0 250.0 % --- xz-plot of temperature distribution / thermal flux mesh 10 2 1000 3000 0 -7.62 7.62 -7.62 7.62 -250.0 250.0
Additional Serpent files
materials file
% --- Fuel materials, TMS limits 557 K and 2100 K: % Fuel1 2.93 wt % enrichment mat fuel1 -10.42 burn 1 tft 557.0 2100.0 rgb 100 0 0 92235.03c -0.0258279 92238.03c -0.85567041 8016.03c -0.11850169 % Fuel2 1.94 wt % enrichment mat fuel2 -10.42 burn 1 tft 557.0 2100.0 rgb 160 0 0 92235.03c -0.01710132 92238.03c -0.86441006 8016.03c -0.11848862 % Fuel3 1.69 wt % enrichment mat fuel3 -10.42 burn 1 tft 557.0 2100.0 rgb 200 75 75 92235.03c -0.0148976 92238.03c -0.86661708 8016.03c -0.11848532 % Fuel4 1.33 wt % enrichment mat fuel4 -10.42 burn 1 tft 557.0 2100.0 rgb 255 150 150 92235.03c -0.01172421 92238.03c -0.86979522 8016.03c -0.11848057 % --- Fuel with Gd, TMS limits 557 K and 2100 K: % Fuel5 2.93 wt % enrichment, 3.0 wt% Gadcontent mat fuel5 -10.25 burn 1 tft 557.0 2100.0 rgb 0 100 0 92235.03c -0.02505306 92238.03c -0.8300003 8016.03c -0.11891791 64152.03c -0.00005029 64154.03c -0.00055541 64155.03c -0.00379519 64156.03c -0.00528302 64157.03c -0.004065 64158.03c -0.00649317 64160.03c -0.00578667 % --- Zirc2 cladding, TMS limits 557 K and 1000 K: mat Zirc2 -6.56000E+00 tft 557.0 1000.0 rgb 200 200 200 8016.03c -1.19376E-03 24052.03c -8.34483E-04 26056.03c -9.16258E-04 28058.03c -3.35317E-04 28060.03c -1.33612E-04 28062.03c -1.91358E-05 40090.03c -4.98111E-01 40091.03c -1.09835E-01 40092.03c -1.69731E-01 40094.03c -1.75753E-01 40096.03c -2.89183E-02 50112.03c -1.27668E-04 50116.03c -1.98205E-03 50117.03c -1.05596E-03 50118.03c -3.35857E-03 50119.03c -1.20129E-03 50120.03c -4.59450E-03 50122.03c -6.63830E-04 50124.03c -8.43778E-04 % --- Assembly box treated as zircaloy, composition is the same as % Zirc2, but has to be separate as the temperature is constant mat box -6.56000E+00 tmp 557.0 rgb 200 200 200 8016.03c -1.19376E-03 24052.03c -8.34483E-04 26056.03c -9.16258E-04 28058.03c -3.35317E-04 28060.03c -1.33612E-04 40090.03c -4.98111E-01 40091.03c -1.09835E-01 40092.03c -1.69731E-01 40094.03c -1.75753E-01 40096.03c -2.89183E-02 50112.03c -1.27668E-04 50116.03c -1.98205E-03 50117.03c -1.05596E-03 50118.03c -3.35857E-03 50119.03c -1.20129E-03 50120.03c -4.59450E-03 50122.03c -6.63830E-04 50124.03c -8.43778E-04 % --- "Steel, Stainless 304" [PNNL-15870, Rev. 1] mat ssteel -8.00000E+00 tmp 557.0 rgb 100 100 100 6012.03c -3.95366E-04 14028.03c -4.59332E-03 14029.03c -2.41681E-04 14030.03c -1.64994E-04 15031.03c -2.30000E-04 16032.03c -1.42073E-04 24050.03c -7.93000E-03 24052.03c -1.59029E-01 24053.03c -1.83798E-02 24054.03c -4.66139E-03 25055.03c -1.00000E-02 26054.03c -3.96166E-02 26056.03c -6.44901E-01 26057.03c -1.51600E-02 26058.03c -2.05287E-03 28058.03c -6.21579E-02 28060.03c -2.47678E-02 28061.03c -1.09461E-03 28062.03c -3.54721E-03 28064.03c -9.32539E-04 % --- Coolant (40% void fraction): mat cool -0.46072 moder lwtr 1001 tmp 557 rgb 150 150 255 1001.03c 0.66667 8016.03c 0.33333 % --- Moderator: mat moder -0.46072 moder lwtr 1001 tmp 557 rgb 50 50 255 1001.03c 0.666667 8016.03c 0.333333 % --- Thermal scattering data for light water: % (HinH20 at 573.60K) therm lwtr lwj3.11t
pins file
% --- Empty lattice position: pin 99 cool % --- Fuel pins: pin 1 fuel1 0.60579 void 0.62103 Zirc2 0.71501 cool pin 2 fuel2 0.60579 void 0.62103 Zirc2 0.71501 cool pin 3 fuel3 0.60579 void 0.62103 Zirc2 0.71501 cool pin 4 fuel4 0.60579 void 0.62103 Zirc2 0.71501 cool pin 5 fuel5 0.60579 void 0.62103 Zirc2 0.71501 cool
geometry file
lat 100 1 0.23876 0.23876 9 9 1.875 % * 99 99 99 99 99 99 99 99 99 99 4 3 3 2 2 2 3 99 99 3 2 1 1 1 1 2 99 99 3 1 5 1 1 5 1 99 99 2 1 1 1 1 1 2 99 99 2 1 1 1 5 1 1 99 99 2 1 5 1 1 1 2 99 99 3 2 1 1 1 2 2 99 99 99 99 99 99 99 99 99 99 % --- Outer channel (assembly pitch = 15.375): surf 1 sqc 0.23876 0.23876 6.70306 % * surf 2 sqc 0.23876 0.23876 6.90626 % --- Axial limits of the active part surf 4 pz -182.88 % Active stack length 365.76 cm surf 5 pz 182.88 % Active stack length 365.76 cm % --- Boundary of one assembly cell surf 9 cuboid -7.62 7.62 -7.62 7.62 -250.0 250.0 % --- Cell definitions: cell 3 101 fill 100 -1 % Pin lattice cell 4 101 box 1 % Channel box wall cell 5 0 fill 101 -2 4 -5 % assembly inside channel box outer wall cell 6 0 moder 2 4 -5 -9 % Water outside channel box cell 9 0 moder -4 -9 % bottom reflector cell 10 0 moder 5 -9 % top reflector cell 99 0 outside 9 % Outside world
volumes file
set mvol fuel1 10 1.05422E+03 fuel1 9 1.05422E+03 fuel1 8 1.05422E+03 fuel1 7 1.05422E+03 fuel1 6 1.05422E+03 fuel1 5 1.05422E+03 fuel1 4 1.05422E+03 fuel1 3 1.05422E+03 fuel1 2 1.05422E+03 fuel1 1 1.05422E+03 fuel2 10 5.48193E+02 fuel2 9 5.48193E+02 fuel2 8 5.48193E+02 fuel2 7 5.48193E+02 fuel2 6 5.48193E+02 fuel2 5 5.48193E+02 fuel2 4 5.48193E+02 fuel2 3 5.48193E+02 fuel2 2 5.48193E+02 fuel2 1 5.48193E+02 fuel3 10 2.53012E+02 fuel3 9 2.53012E+02 fuel3 8 2.53012E+02 fuel3 7 2.53012E+02 fuel3 6 2.53012E+02 fuel3 5 2.53012E+02 fuel3 4 2.53012E+02 fuel3 3 2.53012E+02 fuel3 2 2.53012E+02 fuel3 1 2.53012E+02 fuel4 10 4.21687E+01 fuel4 9 4.21687E+01 fuel4 8 4.21687E+01 fuel4 7 4.21687E+01 fuel4 6 4.21687E+01 fuel4 5 4.21687E+01 fuel4 4 4.21687E+01 fuel4 3 4.21687E+01 fuel4 2 4.21687E+01 fuel4 1 4.21687E+01 fuel5 50 3.37350E+01 fuel5 49 3.37350E+01 fuel5 48 3.37350E+01 fuel5 47 3.37350E+01 fuel5 46 3.37350E+01 fuel5 45 3.37350E+01 fuel5 44 3.37350E+01 fuel5 43 3.37350E+01 fuel5 42 3.37350E+01 fuel5 41 3.37350E+01 fuel5 40 3.37350E+01 fuel5 39 3.37350E+01 fuel5 38 3.37350E+01 fuel5 37 3.37350E+01 fuel5 36 3.37350E+01 fuel5 35 3.37350E+01 fuel5 34 3.37350E+01 fuel5 33 3.37350E+01 fuel5 32 3.37350E+01 fuel5 31 3.37350E+01 fuel5 30 3.37350E+01 fuel5 29 3.37350E+01 fuel5 28 3.37350E+01 fuel5 27 3.37350E+01 fuel5 26 3.37350E+01 fuel5 25 3.37350E+01 fuel5 24 3.37350E+01 fuel5 23 3.37350E+01 fuel5 22 3.37350E+01 fuel5 21 3.37350E+01 fuel5 20 3.37350E+01 fuel5 19 3.37350E+01 fuel5 18 3.37350E+01 fuel5 17 3.37350E+01 fuel5 16 3.37350E+01 fuel5 15 3.37350E+01 fuel5 14 3.37350E+01 fuel5 13 3.37350E+01 fuel5 12 3.37350E+01 fuel5 11 3.37350E+01 fuel5 10 3.37350E+01 fuel5 9 3.37350E+01 fuel5 8 3.37350E+01 fuel5 7 3.37350E+01 fuel5 6 3.37350E+01 fuel5 5 3.37350E+01 fuel5 4 3.37350E+01 fuel5 3 3.37350E+01 fuel5 2 3.37350E+01 fuel5 1 3.37350E+01
FINIX input files
rod_library.txt file
! Peach Bottom 2 BWR rod from UAM description ! No gadolinia begin rod_pb2_nogd pellet_inner_radius = 0.0 pellet_outer_radius = 6.0579e-03 clad_inner_radius = 6.2103e-03 clad_outer_radius = 7.1501e-03 fuel_axial_length = 3.6576 clad_axial_length = 3.6576 plenum_length = 0.4013 pellet_roughness = 2.0e-6 fractional_density = 0.951 gadolinia_weight_fraction = 0.0 clad_roughness = 0.5e-6 coldwork = 0.5 clad_oxygen_concentration = 0.0012 fast_neutron_fluence = 0.0 ! Fill gas pressure (Pa) fill_gas_pressure = 0.69e6 ! As-fabricated fill-gas temperature fill_gas_temperature = 300.0 ! Fill gas fractions gas_fraction_He = 1.0 gas_fraction_Ar = 0.0 gas_fraction_Kr = 0.0 gas_fraction_Xe = 0.0 gas_fraction_H2 = 0.0 gas_fraction_N2 = 0.0 gas_fraction_H2O = 0.0 ! Rod pitch pitch = 18.75e-3 ! Number of rods in unit cell (1.0 in square, 0.5 in triangular lattice) unitcell = 1.0 end rod_pb2_nogd ! Peach Bottom 2 BWR rod from UAM description ! 3.0 wt-% gadolinia begin rod_pb2_yesgd pellet_inner_radius = 0.0 pellet_outer_radius = 6.0579e-03 clad_inner_radius = 6.2103e-03 clad_outer_radius = 7.1501e-03 fuel_axial_length = 3.6576 clad_axial_length = 3.6576 plenum_length = 0.4013 pellet_roughness = 2.0e-6 fractional_density = 0.951 gadolinia_weight_fraction = 0.03 clad_roughness = 0.5e-6 coldwork = 0.5 clad_oxygen_concentration = 0.0012 fast_neutron_fluence = 0.0 ! Fill gas pressure (Pa) fill_gas_pressure = 0.69e6 ! As-fabricated fill-gas temperature fill_gas_temperature = 300.0 ! Fill gas fractions gas_fraction_He = 1.0 gas_fraction_Ar = 0.0 gas_fraction_Kr = 0.0 gas_fraction_Xe = 0.0 gas_fraction_H2 = 0.0 gas_fraction_N2 = 0.0 gas_fraction_H2O = 0.0 ! Rod pitch pitch = 18.75e-3 ! Number of rods in unit cell (1.0 in square, 0.5 in triangular lattice) unitcell = 1.0 end rod_pb2_yesgd
options_library.txt file
! Basic options for the Peach Bottom 2 simulation begin options_pb2_all ! Number of nodes in the thermal/mechanical solution axial_nodes = 10 pellet_radial_nodes = 51 clad_radial_nodes = 21 ! Boundary condition is fixed cladding outer temperature ! NB: This must be given in the scenario boundary_option = 0 end options_pb2_all
scenario_library.txt file
! Basic scenario for Peach Bottom 2 simulations using clad surface temperature ! as a boundary condition begin scenario_pb2_all ! Clad temperature history ! Only one axial zone clad_temperature_history_zones = 3.6576 ! Temperature, time pairs for first axial zone ! Only one time point now clad_temperature_history(1) = 570.0, 0.0 end scenario_pb2_all
References
- ^ Ivanov et al. "Benchmarks for Uncertainty Analysis in Modelling (UAM) for the Design, Operation and Safety Analysis of LWRs, Volume I: Specification and Support Data for Neutronics Cases (Phase I), Version 2.1", NEA/NSC/DOC(2013)7
