Difference between revisions of "HTGR particle-cell burnup example"
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set declib "/xs/sss_endfb7.dec" | set declib "/xs/sss_endfb7.dec" | ||
set nfylib "/xs/sss_endfb7.nfy" | set nfylib "/xs/sss_endfb7.nfy" | ||
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% --- Boundary conditions: | % --- Boundary conditions: | ||
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% ----------------------------------------------------------------------------- | % ----------------------------------------------------------------------------- | ||
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% --- Power density | % --- Power density | ||
Latest revision as of 12:27, 26 May 2022
% ----------------------------------------------------------------------------- set title "HTGR Depletion Benchmark, Infinite Lattice Grain Model" % ----------------------------------------------------------------------------- % Geometry: % ----------------------------------------------------------------------------- % --- Coated particle: particle 1 fuel 0.0250 buffer 0.0340 PyC 0.0380 SiC 0.0415 PyC 0.0455 matrix % --- Lattice cell surf 1 cube 0.0 0.0 0.0 0.081705 cell 1 0 fill 1 -1 cell 2 0 outside 1 % ----------------------------------------------------------------------------- % Material data: % ----------------------------------------------------------------------------- % -- Fuel: mat fuel -10.4 burn 1 92238.03c 2.12877E-02 92235.03c 1.92585E-03 8016.03c 4.64272E-02 5010.03c 1.14694E-07 5011.03c 4.64570E-07 % --- Carbon buffer layer: mat buffer -1.05 moder grph 6000 6000.03c 5.26449E-02 % --- Pyrolytic carbon layer: mat PyC -1.90 moder grph 6000 6000.03c 9.52621E-02 % --- Silicon carbide layer: mat SiC -3.18 14000.03c 4.77240E-02 6000.03c 4.77240E-02 % --- Graphite matrix: mat matrix -1.75 moder grph 6000 burn 1 vol 0.0039689 6000.03c 8.77414E-02 5010.03c 9.64977E-09 5011.03c 3.90864E-08 % --- Thermal scattering data: therm grph gre7.00t % ----------------------------------------------------------------------------- % Calculation parameters: % ----------------------------------------------------------------------------- % --- Geometry plot: plot 3 500 500 % --- Libraries: set acelib "/xs/sss_endfb7u.xsdata" set declib "/xs/sss_endfb7.dec" set nfylib "/xs/sss_endfb7.nfy" % --- Boundary conditions: set bc 3 % --- Histories: set pop 2000 500 10 % ----------------------------------------------------------------------------- % Detectors: % ----------------------------------------------------------------------------- % --- Detector materials: mat m92238 1.0 92238.03c 1.0 mat m92235 1.0 92235.03c 1.0 % --- Energy grid structures: ene 1 1 1E-11 0.625E-6 20.0 ene 2 3 1000 1E-11 20.0 % --- Spectral indices (in fuel): det 1 de 1 dm fuelp1r1 dr 102 m92238 det 2 de 1 dm fuelp1r1 dr 18 m92235 det 3 dm fuelp1r1 dr 18 m92235 dr 18 m92238 det 4 dm fuelp1r1 dr 18 m92235 dr 102 m92238 % --- Spectrum: det 10 de 2 % ----------------------------------------------------------------------------- % Burnup calculation: % ----------------------------------------------------------------------------- % --- Power density set powdens 62.0E-3 % --- Irradiation history: dep butot 0.1 0.5 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0 12.0 14.0 16.0 18.0 20.0 22.0 24.0 26.0 28.0 30.0 32.0 34.0 36.0 38.0 40.0 45.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 % --- Nuclide inventory: set inventory % Actinides: 922350 922380 942390 942400 942410 942420 952410 952440 952450 % Fission products: 360850 380900 471101 551370 541350 621490 621510 % -----------------------------------------------------------------------------
