I’m trying to benchmark a reactor and looking from the data reference of atomic number density it is given in a/b-cm
I cannot write it as a/b-cm, so is it okay if I change it into ‘ao’? or should i calculate it manually by myselft?
fuel = openmc.Material(name=‘Fuel UO2’)
fuel.add_nuclide(‘U235’,3.99198E-3 ,‘ao’)
fuel.add_nuclide(‘U238’,1.92441E-2 ,‘ao’)
fuel.add_nuclide(‘O16’,4.64720E-2 ,‘ao’)
fuel.add_nuclide(‘B10’, 4.06384E-7,‘ao’)
fuel.add_nuclide(‘B11’, 1.63575E-6,‘ao’)
fuel.set_density(‘g/cm3’, 10.4)buffer = openmc.Material(name=‘Buffer’)
buffer.add_element(‘C’, 5.51511E-2, ‘ao’)
buffer.add_nuclide(‘B10’, 1.58513E-8, ‘ao’)
buffer.add_nuclide(‘B11’, 6.38035E-8, ‘ao’)
buffer.set_density(‘g/cm3’, 1.1)
buffer.add_s_alpha_beta(‘c_Graphite’)b4c1 = openmc.Material(name=‘B4C_Poison1’)
b4c1.add_nuclide(‘B10’, 5.30271E-4 , ‘ao’)
b4c1.add_nuclide(‘B11’,2.13441E-3, ‘ao’)
b4c1add_element(‘C’,0.589319E-01, ‘ao’)
b4c1.set_density(‘g/cm3’, 1.59)carbon1 = openmc.Material(name= ‘carbon1’)
carbon1.add_element(‘C’,0.589319E-01, ‘ao’)
carbon1.set_density(‘g/cm3’, 1.59)boronated_carbon1 = openmc.Material.mix_materials([b4c1,carbon1],[0.05,0.95])
boronated_carbon1.set_density(‘g/cm3’, 1.59)
The actual problem is with the keff value in the initial condition. I get around 1.04-1.03 for both in full reactor and core. I suspect it happened due to me describing the material in the wrong way.