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#ATOM NUCLIDE NEW TERMINAL HERE HOW TO#How to set default value in select using ReactJS ?.How to pass data from one component to other component in ReactJS ?.How to redirect to another page in ReactJS ?.How to pass data from child component to its parent in ReactJS ?.Create a Responsive Navbar using ReactJS.How to fetch data from an API in ReactJS ?.ISRO CS Syllabus for Scientist/Engineer Exam.ISRO CS Original Papers and Official Keys.GATE CS Original Papers and Official Keys.RuntimeError: Could not find thermal scattering data c_H_in_H2O in cross_sections.xml file. opt/conda/lib/python3.7/site-packages/openmc/executor.py in _run(args, output, cwd)ģ6 error_msg = ’ '.join(error_msg.split()) opt/conda/lib/python3.7/site-packages/openmc/executor.py in run(particles, threads, geometry_debug, restart_file, tracks, output, cwd, openmc_exec, mpi_args, event_based) RuntimeError Traceback (most recent call last) Geometry = openmc.Geometry(root_universe) Root_universe = openmc.Universe(cells=(fuel, gap, clad, moderator)) Moderator = openmc.Cell(name=‘moderator’)īox = openmc.rectangular_prism(width=pitch, height=pitch, boundary_type='reflective') Water_region = +left & -right & +bottom & -top & +clad_outer_radius Top = openmc.YPlane(y0=pitch/2, boundary_type=‘reflective’) #change to black body for N13 Right = openmc.XPlane(x0=pitch/2, boundary_type=‘reflective’)īottom = openmc.YPlane(y0=-pitch/2, boundary_type=‘reflective’) #change to black body for N13 Left = openmc.XPlane(x0=-pitch/2, boundary_type=‘reflective’) Gap_region = +fuel_outer_radius & -clad_inner_radiusĬlad_region = +clad_inner_radius & -clad_outer_radius ot(width=(2.0, 2,0), basis=‘xz’)įuel_outer_radius = openmc.ZCylinder(r=0.39)Ĭlad_inner_radius = openmc.ZCylinder(r=0.40) #delete laterĬlad_outer_radius = openmc.ZCylinder(r=0.46) #delete later (array(), array())Ĭell = openmc.Cell(region=northern_hemisphere) Uo2_t_density(‘g/cc’, 10.0) Create PuO2 material Zirconium = openmc.Material(name=“zirconium”) 'ao' for atom percent and 'wo' for weight percent Help on method add_nuclide in module openmc.material:Īdd_nuclide(nuclide, percent, percent_type=‘ao’) method of instance My exact input, with the error message at the end is this: #ATOM NUCLIDE NEW TERMINAL HERE CODE#I followed steps 1 to 4, and reran the code in Jupyter Notebooks but unfortunately it did not work. Just copy the cross_sections.xml file and paste it to your working directory.
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