Difference between revisions of "FINIX PB2 example input"
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% --- xz-plot of temperature distribution / thermal flux | % --- xz-plot of temperature distribution / thermal flux | ||
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== References == | == References == | ||
<references/> | <references/> |
Revision as of 14:17, 1 December 2015
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.
Main Serpent input
% --- Asymmetric BWR assembly with Gd-pins ------------------- set title "Peach Bottom 2 from UAM, FINIX calculation" include "/home/vvvillehe/Serpent2/serpdefaults.txt" include pins include geometry % --- Remember to set TMS limits for materials include materials_tft % --- 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 % Name bin1, 6 radial zones in pellet, 24 axial zones finbin bin1 0.0 0.60579 6 -182.88 182.88 24 % --- 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 set pop 5000 10 100 % --- This is the number of iterations set ccmaxiter 10 % --- Use a smaller number of inactive cycles after each FINIX solution % --- (Fission source passing on, number of alternative cycles is 10) set fsp 1 10 % --- Total power set power 3.9429e+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
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