High all,
I remember that a bug related to S(alpha,beta) table of Zr in ZrH matrix has been fixed in 2013.
Now I return back with this message while depleting the U-ZrH fuel using version 0.12.0-dev of openmc
Transport calculation produces good results of Keff while invoking both tables c_H_in_ZrH and c_Zr_in_ZrH. But in depletion calculations only c_H_in_ZrH table is accepted and calculation run perfectely. When I introduce c_Zr_in_ZrH table I get the following error message:
ERROR: Zr90 in material 1 was found in multiple thermal scattering tables. Each nuclide can appear in only one table per material.
The python script contains the following lines :
chain_file = ‘…/depletion_chain/pwr_spectrum_B71_chain.xml’
op = openmc.deplete.Operator(geometry, settings, chain_file)
time_steps = [1., 1., 1., 1., 1., 1., 1., 10.] # days
power = 1000 # W/cm, for 2D simulations only (use W for 3D) 1000 W
integrator = openmc.deplete.PredictorIntegrator(op, time_steps, power, timestep_units=‘d’)
integrator.integrate()
Regards,
Tarek