def test_mcnp6_tally_vol_proton_volume_set():
tally = Tally(
"Flux", "Proton", 12, "Volume", "Volume 12", "Proton Flux in Cell 12", 100.0
)
assert_equal(
"C Proton Flux in Cell 12\n" + "F14:h 12\n" + "SD14 100.000000\n",
tally.mcnp(1, "mcnp6"),
)
def test_mcnp5_tally_surf_flux():
tally = Tally(
"Flux",
"Neutron",
12,
"Surface",
"Surface 12",
"Neutron Flux across surface 12",
-1.0,
)
assert_equal("C Neutron Flux across surface 12\nF12:n 12\n", tally.mcnp(1, "mcnp5"))
def test_mcnp5_tally_surf_current():
tally = Tally(
"Current",
"Neutron",
12,
"Surface",
"Surface 12",
"Neutron Current across surface 12",
-1.0,
)
assert_equal(
"C Neutron Current across surface 12\nF11:n 12\n", tally.mcnp(1, "mcnp5")
)
def test_mcnp5_tally_surf_flux_norm():
tally = Tally(
"Flux",
"Neutron",
12,
"Surface",
"Surface 12",
"Neutron Flux across surface 12",
-1.0,
1.0e13,
)
assert_equal(
"C Neutron Flux across surface 12\nF12:n 12\nFM12 1.000000e+13\n",
tally.mcnp(1, "mcnp5"),
)
def test_mcnp6_tally_vol_norm():
tally = Tally(
"Flux",
"Gamma",
12,
"Volume",
"Volume 12",
"Photon Flux in Cell 12",
-1.0,
1.0e13,
)
assert_equal(
"C Photon Flux in Cell 12\nF14:p 12\nFM14 1.000000e+13\n",
tally.mcnp(1, "mcnp6"),
)
def test_mcnp5_tally_surf_current_norm():
tally = Tally(
"Current",
"Neutron",
12,
"Surface",
"Surface 12",
"Neutron Current across surface 12",
-1.0,
1.0e13,
)
assert_equal(
"C Neutron Current across surface 12\nF11:n 12\nFM11 1.000000e+13\n",
tally.mcnp(1, "mcnp5"),
)
def test_mcnp_mesh_tally_cyl():
particle = "Neutron"
geometry = "Cylinder"
origin = [1, 2, 3]
i_mesh = [5, 10, 20, 25]
j_mesh = [2, 12]
k_mesh = [45]
i_ints = [1, 2, 3, 1]
j_ints = [1]
k_ints = [1]
e = [0, 10, 100]
e_ints = [1, 1, 2]
tal_name = "Mesh Tally XYZ Neutron"
vec = [-1, 4, -2]
axs = [12, -2, 5]
tally = Tally(
particle,
geometry,
origin,
i_mesh,
j_mesh,
k_mesh,
i_ints,
j_ints,
k_ints,
e,
e_ints,
tal_name=tal_name,
axs=axs,
vec=vec,
)
mcnp_tally = (
"C Mesh Tally XYZ Neutron\n"
+ "FMESH14:n GEOM=CYL\n"
+ " AXS=-1.000000 4.000000 -2.000000\n"
+ " VEC=12.000000 -2.000000 5.000000\n"
+ " ORIGIN=1.000000 2.000000 3.000000\n"
+ " IMESH=5.000000 10.000000 20.000000 25.000000 IINTS=1 2 3 1\n"
+ " JMESH=2.000000 12.000000 JINTS=1\n"
+ " KMESH=45.000000 KINTS=1\n"
+ " EMESH=0.000000 10.000000 100.000000\n"
+ " EINTS=1 1 2"
)
assert_equal(mcnp_tally, tally.mcnp(1, "mcnp6"))
def test_mcnp_mesh_tally_xyz():
particle = "Neutron"
geometry = "Cartesian"
origin = [1, 2, 3]
i_mesh = [5, 10, 20, 25]
j_mesh = [2, 12]
k_mesh = [45]
i_ints = [1, 2, 3, 1]
j_ints = [1]
k_ints = [1]
e = [0, 10, 100]
e_ints = [1, 1, 2]
tal_name = "Mesh Tally XYZ Neutron"
out = "IJ"
tally = Tally(
particle,
geometry,
origin,
i_mesh,
j_mesh,
k_mesh,
i_ints,
j_ints,
k_ints,
e,
e_ints,
tal_name=tal_name,
)
mcnp_tally = (
"C Mesh Tally XYZ Neutron\n"
+ "FMESH14:n GEOM=XYZ\n"
+ " ORIGIN=1.000000 2.000000 3.000000\n"
+ " IMESH=5.000000 10.000000 20.000000 25.000000 IINTS=1 2 3 1\n"
+ " JMESH=2.000000 12.000000 JINTS=1\n"
+ " KMESH=45.000000 KINTS=1\n"
+ " EMESH=0.000000 10.000000 100.000000\n"
+ " EINTS=1 1 2\n"
+ " OUT=IJ"
)
assert_equal(mcnp_tally, tally.mcnp(1, "mcnp6", out))
def test_mcnp5_tally_surf_current():
tally = Tally("Current","Neutron",12,"Surface","Surface 12","Neutron Current across surface 12",-1.0)
assert_equal("C Neutron Current across surface 12\nF11:N 12\n",tally.mcnp(1,"mcnp5"))
def test_mcnp6_tally_vol_proton():
tally = Tally(
"Flux", "Proton", 12, "Volume", "Volume 12", "Proton Flux in Cell 12", -1.0
)
assert_equal("C Proton Flux in Cell 12\nF14:h 12\n", tally.mcnp(1, "mcnp6"))
def test_mcnp5_tally_surf_flux():
tally = Tally("Flux","Neutron",12,"Surface","Surface 12","Neutron Flux across surface 12",-1.0)
assert_equal("C Neutron Flux across surface 12\nF12:N 12\n",tally.mcnp(1,"mcnp5"))
def test_mcnp6_tally_vol():
tally = Tally(
"Flux", "Gamma", 12, "Volume", "Volume 12", "Photon Flux in Cell 12", -1.0
)
assert_equal("C Photon Flux in Cell 12\nF14:p 12\n", tally.mcnp(1, "mcnp6"))
def test_mcnp5_tally_surf_flux_norm():
tally = Tally("Flux","Neutron",12,"Surface","Surface 12","Neutron Flux across surface 12",-1.0,1.0e13)
assert_equal("C Neutron Flux across surface 12\nF12:N 12\nFM12 1.000000e+13\n",tally.mcnp(1,"mcnp5"))
def test_mcnp6_tally_vol():
tally = Tally("Flux","Gamma",12,"Volume","Volume 12","Photon Flux in Cell 12",-1.0)
assert_equal("C Photon Flux in Cell 12\nF14:P 12\n",tally.mcnp(1,"mcnp6"))
def test_mcnp6_tally_vol_norm():
tally = Tally("Flux","Gamma",12,"Volume","Volume 12","Photon Flux in Cell 12",-1.0,1.0e13)
assert_equal("C Photon Flux in Cell 12\nF14:P 12\nFM14 1.000000e+13\n",tally.mcnp(1,"mcnp6"))
def test_mcnp5_tally_surf_current_norm():
tally = Tally("Current","Neutron",12,"Surface","Surface 12","Neutron Current across surface 12",-1.0,1.0e13)
assert_equal("C Neutron Current across surface 12\nF11:N 12\nFM11 1.000000e+13\n",tally.mcnp(1,"mcnp5"))
def test_mcnp6_tally_vol_proton():
tally = Tally("Flux","Proton",12,"Volume","Volume 12","Proton Flux in Cell 12",-1.0)
assert_equal("C Proton Flux in Cell 12\nF14:H 12\n",tally.mcnp(1,"mcnp6"))
def test_mcnp6_tally_vol_proton_volume_set():
tally = Tally("Flux","Proton",12,"Volume","Volume 12","Proton Flux in Cell 12",100.0)
assert_equal("C Proton Flux in Cell 12\n"+\
"F14:H 12\n"+\
"SD14 100.000000\n",tally.mcnp(1,"mcnp6"))
