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Update the diff tally testing
This commit is contained in:
Sterling Harper
parent
cbe4c55e65
commit
453d395bcd
17 changed files with 221 additions and 526 deletions
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@ -1,150 +0,0 @@
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import openmc
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def make_mats(mod_density=0.7420582):
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water = openmc.Material(name='water')
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water.set_density('g/cm3', mod_density)
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water.add_nuclide(openmc.Nuclide('H-1'), 2.0)
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water.add_nuclide(openmc.Nuclide('O-16'), 1.0)
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fuel = openmc.Material(name='fuel 2.4%')
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fuel.set_density('g/cm3', 10.29769)
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fuel.add_nuclide(openmc.Nuclide('U-234'), 5.7987e-06)
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fuel.add_nuclide(openmc.Nuclide('U-235'), 7.2175e-04)
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fuel.add_nuclide(openmc.Nuclide('U-238'), 2.2253e-02)
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fuel.add_nuclide(openmc.Nuclide('O-16'), 4.5750e-02)
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fuel.add_nuclide(openmc.Nuclide('O-17'), 9.4222e-05)
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zirc4 = openmc.Material(name='zircaloy 4')
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zirc4.set_density('g/cm3', 6.55)
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zirc4.add_nuclide(openmc.Nuclide('O-16'), 3.0743e-04)
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zirc4.add_nuclide(openmc.Nuclide('O-17'), 1.1711e-07)
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# O-18 omitted
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zirc4.add_nuclide(openmc.Nuclide('Cr-50'), 3.2962e-06)
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zirc4.add_nuclide(openmc.Nuclide('Cr-52'), 6.3564e-05)
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zirc4.add_nuclide(openmc.Nuclide('Cr-53'), 7.2076e-06)
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zirc4.add_nuclide(openmc.Nuclide('Cr-54'), 1.7941e-06)
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zirc4.add_nuclide(openmc.Nuclide('Fe-54'), 8.6699e-06)
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zirc4.add_nuclide(openmc.Nuclide('Fe-56'), 1.3610e-04)
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zirc4.add_nuclide(openmc.Nuclide('Fe-57'), 3.1431e-06)
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zirc4.add_nuclide(openmc.Nuclide('Fe-58'), 4.1829e-07)
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zirc4.add_nuclide(openmc.Nuclide('Zr-90'), 2.1827e-02)
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zirc4.add_nuclide(openmc.Nuclide('Zr-91'), 4.7600e-03)
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zirc4.add_nuclide(openmc.Nuclide('Zr-92'), 7.2758e-03)
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zirc4.add_nuclide(openmc.Nuclide('Zr-94'), 7.3734e-03)
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zirc4.add_nuclide(openmc.Nuclide('Zr-96'), 1.1879e-03)
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zirc4.add_nuclide(openmc.Nuclide('Sn-112'), 4.6735e-06)
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zirc4.add_nuclide(openmc.Nuclide('Sn-114'), 3.1799e-06)
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zirc4.add_nuclide(openmc.Nuclide('Sn-115'), 1.6381e-06)
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zirc4.add_nuclide(openmc.Nuclide('Sn-116'), 7.0055e-05)
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zirc4.add_nuclide(openmc.Nuclide('Sn-117'), 3.7003e-05)
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zirc4.add_nuclide(openmc.Nuclide('Sn-118'), 1.1669e-04)
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zirc4.add_nuclide(openmc.Nuclide('Sn-119'), 4.1387e-05)
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zirc4.add_nuclide(openmc.Nuclide('Sn-120'), 1.5697e-04)
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zirc4.add_nuclide(openmc.Nuclide('Sn-122'), 2.2308e-05)
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zirc4.add_nuclide(openmc.Nuclide('Sn-124'), 2.7897e-05)
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materials_file = openmc.MaterialsFile()
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materials_file.default_xs = '71c'
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materials_file.add_materials([water, fuel, zirc4])
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return (materials_file,
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{'mod':water,
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'fuel':fuel,
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'clad':zirc4})
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def make_geom(mats):
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# Instantiate surfaces.
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rfo = openmc.ZCylinder(x0=0.0, y0=0.0, R=0.39218, name='fuel outer')
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rci = openmc.ZCylinder(x0=0.0, y0=0.0, R=0.40005, name='clad inner')
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rco = openmc.ZCylinder(x0=0.0, y0=0.0, R=0.45720, name='clad outer')
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x0 = openmc.XPlane(x0=-0.62992)
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x1 = openmc.XPlane(x0=0.62992)
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y0 = openmc.YPlane(y0=-0.62992)
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y1 = openmc.YPlane(y0=0.62992)
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z0 = openmc.ZPlane(z0=-1.0)
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z1 = openmc.ZPlane(z0=1.0)
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x0.boundary_type = 'reflective'
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x1.boundary_type = 'reflective'
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y0.boundary_type = 'reflective'
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y1.boundary_type = 'reflective'
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z0.boundary_type = 'reflective'
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z1.boundary_type = 'reflective'
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# Instantiate cells.
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fuel_c = openmc.Cell(name='fuel')
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fuel_c.add_surface(rfo, halfspace=-1)
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fuel_c.add_surface(z0, halfspace=+1)
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fuel_c.add_surface(z1, halfspace=-1)
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gap = openmc.Cell(name='gap')
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gap.add_surface(rci, halfspace=-1)
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gap.add_surface(rfo, halfspace=+1)
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gap.add_surface(z0, halfspace=+1)
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gap.add_surface(z1, halfspace=-1)
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clad_c = openmc.Cell(name='clad')
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clad_c.add_surface(rco, halfspace=-1)
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clad_c.add_surface(rci, halfspace=+1)
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clad_c.add_surface(z0, halfspace=+1)
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clad_c.add_surface(z1, halfspace=-1)
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mod_c = openmc.Cell(name='moderator')
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mod_c.add_surface(rco, halfspace=+1)
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mod_c.add_surface(x0, halfspace=+1)
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mod_c.add_surface(x1, halfspace=-1)
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mod_c.add_surface(y0, halfspace=+1)
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mod_c.add_surface(y1, halfspace=-1)
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mod_c.add_surface(z0, halfspace=+1)
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mod_c.add_surface(z1, halfspace=-1)
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# Add materials to cells.
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fuel_c.fill = mats['fuel']
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gap.fill = 'void'
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clad_c.fill = mats['clad']
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mod_c.fill = mats['mod']
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# Instantiate universes.
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u0 = openmc.Universe(universe_id=0)
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u0.add_cells([fuel_c, gap, clad_c, mod_c])
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# Write the XML file.
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geometry = openmc.Geometry()
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geometry.root_universe = u0
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geometry_file = openmc.GeometryFile()
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geometry_file.geometry = geometry
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return geometry_file
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def make_settings(**kwargs):
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if 'batches' in kwargs:
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batches = kwargs['batches']
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settings_file = openmc.SettingsFile()
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settings_file.batches = kwargs.setdefault('batches', 100)
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settings_file.inactive = kwargs.setdefault('inactive', 10)
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settings_file.particles = kwargs.setdefault('particles', 1000)
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settings_file.set_source_space('box', (-0.6, -0.6, -0.9,
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0.6, 0.6, 0.9))
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settings_file.entropy_lower_left = (-0.7, -0.7, -1.1)
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settings_file.entropy_upper_right = (0.7, 0.7, 1.1)
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settings_file.entropy_dimension = (10, 10, 10)
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return settings_file
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def make_inputs(mod_density=0.7420582, **kwargs):
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(mat_file, mats) = make_mats(mod_density)
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mat_file.export_to_xml()
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geo_file = make_geom(mats)
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geo_file.export_to_xml()
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sets_file = make_settings(**kwargs)
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sets_file.export_to_xml()
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if __name__ == '__main__':
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make_inputs(inactive=5, batches=10, particles=100)
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@ -1,16 +0,0 @@
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<?xml version='1.0' encoding='utf-8'?>
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<geometry>
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<cell id="10000" material="10001" name="fuel" region="(-10000 10007 -10008)" universe="0" />
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<cell id="10001" material="void" name="gap" region="(-10001 10000 10007 -10008)" universe="0" />
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<cell id="10002" material="10002" name="clad" region="(-10002 10001 10007 -10008)" universe="0" />
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<cell id="10003" material="10000" name="moderator" region="(10002 10003 -10004 10005 -10006 10007 -10008)" universe="0" />
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<surface boundary="transmission" coeffs="0.0 0.0 0.39218" id="10000" name="fuel outer" type="z-cylinder" />
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<surface boundary="transmission" coeffs="0.0 0.0 0.40005" id="10001" name="clad inner" type="z-cylinder" />
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<surface boundary="transmission" coeffs="0.0 0.0 0.4572" id="10002" name="clad outer" type="z-cylinder" />
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<surface boundary="reflective" coeffs="-0.62992" id="10003" type="x-plane" />
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<surface boundary="reflective" coeffs="0.62992" id="10004" type="x-plane" />
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<surface boundary="reflective" coeffs="-0.62992" id="10005" type="y-plane" />
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<surface boundary="reflective" coeffs="0.62992" id="10006" type="y-plane" />
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<surface boundary="reflective" coeffs="-1.0" id="10007" type="z-plane" />
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<surface boundary="reflective" coeffs="1.0" id="10008" type="z-plane" />
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</geometry>
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@ -1,45 +0,0 @@
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<?xml version='1.0' encoding='utf-8'?>
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<materials>
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<default_xs>71c</default_xs>
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<material id="10000" name="water">
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<density units="g/cm3" value="0.7420582" />
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<nuclide ao="2.0" name="H-1" />
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<nuclide ao="1.0" name="O-16" />
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</material>
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<material id="10001" name="fuel 2.4%">
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<density units="g/cm3" value="10.29769" />
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<nuclide ao="5.7987e-06" name="U-234" />
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<nuclide ao="0.00072175" name="U-235" />
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<nuclide ao="0.022253" name="U-238" />
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<nuclide ao="0.04575" name="O-16" />
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<nuclide ao="9.4222e-05" name="O-17" />
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</material>
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<material id="10002" name="zircaloy 4">
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<density units="g/cm3" value="6.55" />
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<nuclide ao="0.00030743" name="O-16" />
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<nuclide ao="1.1711e-07" name="O-17" />
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<nuclide ao="3.2962e-06" name="Cr-50" />
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<nuclide ao="6.3564e-05" name="Cr-52" />
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<nuclide ao="7.2076e-06" name="Cr-53" />
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<nuclide ao="1.7941e-06" name="Cr-54" />
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<nuclide ao="8.6699e-06" name="Fe-54" />
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<nuclide ao="0.0001361" name="Fe-56" />
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<nuclide ao="3.1431e-06" name="Fe-57" />
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<nuclide ao="4.1829e-07" name="Fe-58" />
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<nuclide ao="0.021827" name="Zr-90" />
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<nuclide ao="0.00476" name="Zr-91" />
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<nuclide ao="0.0072758" name="Zr-92" />
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<nuclide ao="0.0073734" name="Zr-94" />
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<nuclide ao="0.0011879" name="Zr-96" />
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<nuclide ao="4.6735e-06" name="Sn-112" />
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<nuclide ao="3.1799e-06" name="Sn-114" />
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<nuclide ao="1.6381e-06" name="Sn-115" />
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<nuclide ao="7.0055e-05" name="Sn-116" />
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<nuclide ao="3.7003e-05" name="Sn-117" />
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<nuclide ao="0.00011669" name="Sn-118" />
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<nuclide ao="4.1387e-05" name="Sn-119" />
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<nuclide ao="0.00015697" name="Sn-120" />
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<nuclide ao="2.2308e-05" name="Sn-122" />
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<nuclide ao="2.7897e-05" name="Sn-124" />
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</material>
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</materials>
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k-combined:
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1.502605E+00 2.273838E-02
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tally 1:
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5.280104E+00
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1.379258E+01
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@ -1,18 +0,0 @@
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<?xml version='1.0' encoding='utf-8'?>
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<settings>
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<eigenvalue>
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<particles>100</particles>
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<batches>10</batches>
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<inactive>5</inactive>
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</eigenvalue>
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<source>
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<space type="box">
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<parameters>-0.6 -0.6 -0.9 0.6 0.6 0.9</parameters>
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</space>
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</source>
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<entropy>
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<dimension>10 10 10</dimension>
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<lower_left>-0.7 -0.7 -1.1</lower_left>
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<upper_right>0.7 0.7 1.1</upper_right>
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</entropy>
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</settings>
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<?xml version='1.0' encoding='utf-8'?>
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<tallies>
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<tally id="1">
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<scores>keff</scores>
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<derivative variable="density" material="10000"/>
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</tally>
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</tallies>
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#!/usr/bin/env python
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import os
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import sys
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sys.path.insert(0, os.pardir)
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from testing_harness import TestHarness
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if __name__ == '__main__':
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harness = TestHarness('statepoint.10.*', True)
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harness.main()
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import openmc
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def make_mats(**kwargs):
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water_dict = {
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'B-10': 8.0042e-06,
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'B-11': 3.2218e-05,
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'H-1': 4.9457e-02,
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'H-2': 7.4196e-06,
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'O-16': 2.4672e-02,
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'O-17': 9.3982e-06 + 5.0701e-05}
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water = openmc.Material(name='water')
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water.set_density('sum')
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for nuclide in water_dict:
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water.add_nuclide(nuclide, water_dict[nuclide])
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U235_dens = kwargs.setdefault('U235_dens', 5.5814e-04)
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fuel_dict = {
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'B-10': 8.0042e-06,
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'U-234': 4.4842e-06,
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'U-235': U235_dens,
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'U-238': 2.2407e-02,
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'O-16': 4.5828e-02,
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'O-17': 1.7457e-05 + 9.4176e-05}
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fuel = openmc.Material(name='fuel 2.4%')
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fuel.set_density('sum')
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for nuclide in fuel_dict:
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fuel.add_nuclide(nuclide, fuel_dict[nuclide])
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zirc4_dict = {
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'O-16': 3.0743e-04,
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'O-17': 1.1711e-07 + 6.3176e-07,
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'Cr-50': 3.2962e-06,
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'Cr-52': 6.3564e-05,
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'Cr-53': 7.2076e-06,
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'Cr-54': 1.7941e-06,
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'Fe-54': 8.6699e-06,
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'Fe-56': 1.3610e-04,
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'Fe-57': 3.1431e-06,
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'Fe-58': 4.1829e-07,
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'Zr-90': 2.1827e-02,
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'Zr-91': 4.7600e-03,
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'Zr-92': 7.2758e-03,
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'Zr-94': 7.3734e-03,
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'Zr-96': 1.1879e-03,
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'Sn-112': 4.6735e-06,
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'Sn-114': 3.1799e-06,
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'Sn-115': 1.6381e-06,
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'Sn-116': 7.0055e-05,
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'Sn-117': 3.7003e-05,
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'Sn-118': 1.1669e-04,
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'Sn-119': 4.1387e-05,
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'Sn-120': 1.5697e-04,
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'Sn-122': 2.2308e-05,
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'Sn-124': 2.7897e-05}
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zirc4 = openmc.Material(name='zircaloy 4')
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zirc4.set_density('sum')
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for nuclide in zirc4_dict:
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zirc4.add_nuclide(nuclide, zirc4_dict[nuclide])
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materials_file = openmc.MaterialsFile()
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materials_file.default_xs = '71c'
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materials_file.add_materials([water, fuel, zirc4])
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return (materials_file,
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{'mod':water,
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'fuel':fuel,
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'clad':zirc4})
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def make_geom(mats):
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# Instantiate surfaces.
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rfo = openmc.ZCylinder(x0=0.0, y0=0.0, R=0.39218, name='fuel outer')
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rci = openmc.ZCylinder(x0=0.0, y0=0.0, R=0.40005, name='clad inner')
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rco = openmc.ZCylinder(x0=0.0, y0=0.0, R=0.45720, name='clad outer')
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x0 = openmc.XPlane(x0=-0.62992)
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x1 = openmc.XPlane(x0=0.62992)
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y0 = openmc.YPlane(y0=-0.62992)
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y1 = openmc.YPlane(y0=0.62992)
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z0 = openmc.ZPlane(z0=-1.0)
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z1 = openmc.ZPlane(z0=1.0)
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x0.boundary_type = 'reflective'
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x1.boundary_type = 'reflective'
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y0.boundary_type = 'reflective'
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y1.boundary_type = 'reflective'
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z0.boundary_type = 'reflective'
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z1.boundary_type = 'reflective'
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# Instantiate cells.
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fuel_c = openmc.Cell(name='fuel')
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fuel_c.add_surface(rfo, halfspace=-1)
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fuel_c.add_surface(z0, halfspace=+1)
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fuel_c.add_surface(z1, halfspace=-1)
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||||
gap = openmc.Cell(name='gap')
|
||||
gap.add_surface(rci, halfspace=-1)
|
||||
gap.add_surface(rfo, halfspace=+1)
|
||||
gap.add_surface(z0, halfspace=+1)
|
||||
gap.add_surface(z1, halfspace=-1)
|
||||
|
||||
clad_c = openmc.Cell(name='clad')
|
||||
clad_c.add_surface(rco, halfspace=-1)
|
||||
clad_c.add_surface(rci, halfspace=+1)
|
||||
clad_c.add_surface(z0, halfspace=+1)
|
||||
clad_c.add_surface(z1, halfspace=-1)
|
||||
|
||||
mod_c = openmc.Cell(name='moderator')
|
||||
mod_c.add_surface(rco, halfspace=+1)
|
||||
mod_c.add_surface(x0, halfspace=+1)
|
||||
mod_c.add_surface(x1, halfspace=-1)
|
||||
mod_c.add_surface(y0, halfspace=+1)
|
||||
mod_c.add_surface(y1, halfspace=-1)
|
||||
mod_c.add_surface(z0, halfspace=+1)
|
||||
mod_c.add_surface(z1, halfspace=-1)
|
||||
|
||||
# Add materials to cells.
|
||||
fuel_c.fill = mats['fuel']
|
||||
gap.fill = 'void'
|
||||
clad_c.fill = mats['clad']
|
||||
mod_c.fill = mats['mod']
|
||||
|
||||
# Instantiate universes.
|
||||
u0 = openmc.Universe(universe_id=0)
|
||||
u0.add_cells([fuel_c, gap, clad_c, mod_c])
|
||||
|
||||
# Write the XML file.
|
||||
geometry = openmc.Geometry()
|
||||
geometry.root_universe = u0
|
||||
geometry_file = openmc.GeometryFile()
|
||||
geometry_file.geometry = geometry
|
||||
|
||||
return geometry_file
|
||||
|
||||
|
||||
def make_settings(**kwargs):
|
||||
if 'batches' in kwargs:
|
||||
batches = kwargs['batches']
|
||||
|
||||
settings_file = openmc.SettingsFile()
|
||||
settings_file.batches = kwargs.setdefault('batches', 1610)
|
||||
settings_file.inactive = kwargs.setdefault('inactive', 10)
|
||||
settings_file.particles = kwargs.setdefault('particles', 1000)
|
||||
settings_file.set_source_space('box', (-0.6, -0.6, -0.9,
|
||||
0.6, 0.6, 0.9))
|
||||
settings_file.entropy_lower_left = (-0.7, -0.7, -1.1)
|
||||
settings_file.entropy_upper_right = (0.7, 0.7, 1.1)
|
||||
settings_file.entropy_dimension = (10, 10, 10)
|
||||
return settings_file
|
||||
|
||||
|
||||
def make_inputs(**kwargs):
|
||||
(mat_file, mats) = make_mats(**kwargs)
|
||||
mat_file.export_to_xml()
|
||||
|
||||
geo_file = make_geom(mats)
|
||||
geo_file.export_to_xml()
|
||||
|
||||
sets_file = make_settings(**kwargs)
|
||||
sets_file.export_to_xml()
|
||||
|
||||
|
||||
if __name__ == '__main__':
|
||||
make_inputs(inactive=5, batches=10, particles=100)
|
||||
|
|
@ -1,16 +0,0 @@
|
|||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<geometry>
|
||||
<cell id="10000" material="10001" name="fuel" region="(-10000 10007 -10008)" universe="0" />
|
||||
<cell id="10001" material="void" name="gap" region="(-10001 10000 10007 -10008)" universe="0" />
|
||||
<cell id="10002" material="10002" name="clad" region="(-10002 10001 10007 -10008)" universe="0" />
|
||||
<cell id="10003" material="10000" name="moderator" region="(10002 10003 -10004 10005 -10006 10007 -10008)" universe="0" />
|
||||
<surface boundary="transmission" coeffs="0.0 0.0 0.39218" id="10000" name="fuel outer" type="z-cylinder" />
|
||||
<surface boundary="transmission" coeffs="0.0 0.0 0.40005" id="10001" name="clad inner" type="z-cylinder" />
|
||||
<surface boundary="transmission" coeffs="0.0 0.0 0.4572" id="10002" name="clad outer" type="z-cylinder" />
|
||||
<surface boundary="reflective" coeffs="-0.62992" id="10003" type="x-plane" />
|
||||
<surface boundary="reflective" coeffs="0.62992" id="10004" type="x-plane" />
|
||||
<surface boundary="reflective" coeffs="-0.62992" id="10005" type="y-plane" />
|
||||
<surface boundary="reflective" coeffs="0.62992" id="10006" type="y-plane" />
|
||||
<surface boundary="reflective" coeffs="-1.0" id="10007" type="z-plane" />
|
||||
<surface boundary="reflective" coeffs="1.0" id="10008" type="z-plane" />
|
||||
</geometry>
|
||||
|
|
@ -1,50 +0,0 @@
|
|||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<materials>
|
||||
<default_xs>71c</default_xs>
|
||||
<material id="10000" name="water">
|
||||
<density units="sum" />
|
||||
<nuclide ao="6.00992e-05" name="O-17" />
|
||||
<nuclide ao="0.024672" name="O-16" />
|
||||
<nuclide ao="8.0042e-06" name="B-10" />
|
||||
<nuclide ao="3.2218e-05" name="B-11" />
|
||||
<nuclide ao="0.049457" name="H-1" />
|
||||
<nuclide ao="7.4196e-06" name="H-2" />
|
||||
</material>
|
||||
<material id="10001" name="fuel 2.4%">
|
||||
<density units="sum" />
|
||||
<nuclide ao="0.022407" name="U-238" />
|
||||
<nuclide ao="0.000111633" name="O-17" />
|
||||
<nuclide ao="8.0042e-06" name="B-10" />
|
||||
<nuclide ao="0.045828" name="O-16" />
|
||||
<nuclide ao="4.4842e-06" name="U-234" />
|
||||
<nuclide ao="0.00055814" name="U-235" />
|
||||
</material>
|
||||
<material id="10002" name="zircaloy 4">
|
||||
<density units="sum" />
|
||||
<nuclide ao="0.00011669" name="Sn-118" />
|
||||
<nuclide ao="4.1387e-05" name="Sn-119" />
|
||||
<nuclide ao="4.6735e-06" name="Sn-112" />
|
||||
<nuclide ao="3.1799e-06" name="Sn-114" />
|
||||
<nuclide ao="1.6381e-06" name="Sn-115" />
|
||||
<nuclide ao="7.0055e-05" name="Sn-116" />
|
||||
<nuclide ao="3.7003e-05" name="Sn-117" />
|
||||
<nuclide ao="0.0001361" name="Fe-56" />
|
||||
<nuclide ao="3.1431e-06" name="Fe-57" />
|
||||
<nuclide ao="8.6699e-06" name="Fe-54" />
|
||||
<nuclide ao="4.1829e-07" name="Fe-58" />
|
||||
<nuclide ao="0.0072758" name="Zr-92" />
|
||||
<nuclide ao="2.7897e-05" name="Sn-124" />
|
||||
<nuclide ao="0.00015697" name="Sn-120" />
|
||||
<nuclide ao="2.2308e-05" name="Sn-122" />
|
||||
<nuclide ao="1.7941e-06" name="Cr-54" />
|
||||
<nuclide ao="6.3564e-05" name="Cr-52" />
|
||||
<nuclide ao="7.2076e-06" name="Cr-53" />
|
||||
<nuclide ao="3.2962e-06" name="Cr-50" />
|
||||
<nuclide ao="7.4887e-07" name="O-17" />
|
||||
<nuclide ao="0.00030743" name="O-16" />
|
||||
<nuclide ao="0.00476" name="Zr-91" />
|
||||
<nuclide ao="0.021827" name="Zr-90" />
|
||||
<nuclide ao="0.0011879" name="Zr-96" />
|
||||
<nuclide ao="0.0073734" name="Zr-94" />
|
||||
</material>
|
||||
</materials>
|
||||
|
|
@ -1,5 +0,0 @@
|
|||
k-combined:
|
||||
1.055198E+00 5.785829E-02
|
||||
tally 1:
|
||||
2.547151E+03
|
||||
1.303757E+06
|
||||
|
|
@ -1,18 +0,0 @@
|
|||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<settings>
|
||||
<eigenvalue>
|
||||
<particles>100</particles>
|
||||
<batches>10</batches>
|
||||
<inactive>5</inactive>
|
||||
</eigenvalue>
|
||||
<source>
|
||||
<space type="box">
|
||||
<parameters>-0.6 -0.6 -0.9 0.6 0.6 0.9</parameters>
|
||||
</space>
|
||||
</source>
|
||||
<entropy>
|
||||
<dimension>10 10 10</dimension>
|
||||
<lower_left>-0.7 -0.7 -1.1</lower_left>
|
||||
<upper_right>0.7 0.7 1.1</upper_right>
|
||||
</entropy>
|
||||
</settings>
|
||||
|
|
@ -1,10 +0,0 @@
|
|||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<tallies>
|
||||
<tally id="1">
|
||||
<scores>keff</scores>
|
||||
<!--
|
||||
<derivative variable="density" material="10000"/>
|
||||
-->
|
||||
<derivative variable="nuclide_density" material="10001" nuclide="U-235.71c"/>
|
||||
</tally>
|
||||
</tallies>
|
||||
|
|
@ -1,11 +0,0 @@
|
|||
#!/usr/bin/env python
|
||||
|
||||
import os
|
||||
import sys
|
||||
sys.path.insert(0, os.pardir)
|
||||
from testing_harness import TestHarness
|
||||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = TestHarness('statepoint.10.*', True)
|
||||
harness.main()
|
||||
1
tests/test_diff_tally/inputs_true.dat
Normal file
1
tests/test_diff_tally/inputs_true.dat
Normal file
|
|
@ -0,0 +1 @@
|
|||
cb132b2211831bf333bc9be0b10d092ad3bbe9a188743cf4c430ae97037987763b268997757a0602c164d8c2deb3eb9843590d860ba5a4858092a9ad0b8adeba
|
||||
97
tests/test_diff_tally/results_true.dat
Normal file
97
tests/test_diff_tally/results_true.dat
Normal file
|
|
@ -0,0 +1,97 @@
|
|||
d_material,d_nuclide,d_variable,score,mean,std. dev.
|
||||
3,,density,flux,-5.12e+00,8.94e-01
|
||||
3,,density,flux,-1.07e+01,8.84e-01
|
||||
1,,density,flux,-3.14e-01,4.48e-02
|
||||
1,,density,flux,-2.73e-01,8.51e-02
|
||||
1,O-16.71c,nuclide_density,flux,-3.58e+00,7.77e+00
|
||||
1,O-16.71c,nuclide_density,flux,-7.64e+00,1.09e+01
|
||||
1,U-235.71c,nuclide_density,flux,-1.19e+03,1.18e+02
|
||||
1,U-235.71c,nuclide_density,flux,-1.25e+03,1.63e+02
|
||||
3,,density,total,-1.92e+00,4.49e-01
|
||||
3,,density,absorption,5.89e-02,6.68e-02
|
||||
3,,density,fission,8.55e-02,3.33e-02
|
||||
3,,density,nu-fission,2.20e-01,8.60e-02
|
||||
3,,density,total,4.49e-02,3.15e-02
|
||||
3,,density,absorption,6.66e-02,2.74e-02
|
||||
3,,density,fission,6.12e-02,2.24e-02
|
||||
3,,density,nu-fission,1.49e-01,5.45e-02
|
||||
3,,density,total,7.72e+00,9.45e-01
|
||||
3,,density,absorption,1.26e-01,2.24e-02
|
||||
3,,density,fission,0.00e+00,0.00e+00
|
||||
3,,density,nu-fission,0.00e+00,0.00e+00
|
||||
3,,density,total,0.00e+00,0.00e+00
|
||||
3,,density,absorption,0.00e+00,0.00e+00
|
||||
3,,density,fission,0.00e+00,0.00e+00
|
||||
3,,density,nu-fission,0.00e+00,0.00e+00
|
||||
1,,density,total,3.79e-01,1.14e-02
|
||||
1,,density,absorption,1.27e-02,4.48e-03
|
||||
1,,density,fission,1.88e-03,1.96e-03
|
||||
1,,density,nu-fission,5.22e-03,5.08e-03
|
||||
1,,density,total,5.43e-03,1.67e-03
|
||||
1,,density,absorption,1.29e-03,1.64e-03
|
||||
1,,density,fission,3.13e-05,1.30e-03
|
||||
1,,density,nu-fission,1.12e-04,3.17e-03
|
||||
1,,density,total,-2.91e-01,9.67e-02
|
||||
1,,density,absorption,-5.40e-03,1.29e-03
|
||||
1,,density,fission,0.00e+00,0.00e+00
|
||||
1,,density,nu-fission,0.00e+00,0.00e+00
|
||||
1,,density,total,0.00e+00,0.00e+00
|
||||
1,,density,absorption,0.00e+00,0.00e+00
|
||||
1,,density,fission,0.00e+00,0.00e+00
|
||||
1,,density,nu-fission,0.00e+00,0.00e+00
|
||||
1,O-16.71c,nuclide_density,total,4.33e+01,3.24e+00
|
||||
1,O-16.71c,nuclide_density,absorption,6.59e-01,5.83e-01
|
||||
1,O-16.71c,nuclide_density,fission,4.31e-01,1.26e-01
|
||||
1,O-16.71c,nuclide_density,nu-fission,1.08e+00,3.25e-01
|
||||
1,O-16.71c,nuclide_density,total,4.52e-01,1.50e-01
|
||||
1,O-16.71c,nuclide_density,absorption,4.58e-01,1.12e-01
|
||||
1,O-16.71c,nuclide_density,fission,3.54e-01,9.55e-02
|
||||
1,O-16.71c,nuclide_density,nu-fission,8.62e-01,2.33e-01
|
||||
1,O-16.71c,nuclide_density,total,-4.58e-01,1.17e+01
|
||||
1,O-16.71c,nuclide_density,absorption,1.23e-01,1.75e-01
|
||||
1,O-16.71c,nuclide_density,fission,0.00e+00,0.00e+00
|
||||
1,O-16.71c,nuclide_density,nu-fission,0.00e+00,0.00e+00
|
||||
1,O-16.71c,nuclide_density,total,0.00e+00,0.00e+00
|
||||
1,O-16.71c,nuclide_density,absorption,0.00e+00,0.00e+00
|
||||
1,O-16.71c,nuclide_density,fission,0.00e+00,0.00e+00
|
||||
1,O-16.71c,nuclide_density,nu-fission,0.00e+00,0.00e+00
|
||||
1,U-235.71c,nuclide_density,total,-2.41e+02,5.64e+01
|
||||
1,U-235.71c,nuclide_density,absorption,1.11e+02,1.40e+01
|
||||
1,U-235.71c,nuclide_density,fission,1.79e+02,9.60e+00
|
||||
1,U-235.71c,nuclide_density,nu-fission,3.97e+02,2.44e+01
|
||||
1,U-235.71c,nuclide_density,total,4.56e+02,1.09e+01
|
||||
1,U-235.71c,nuclide_density,absorption,3.45e+02,1.09e+01
|
||||
1,U-235.71c,nuclide_density,fission,2.70e+02,8.42e+00
|
||||
1,U-235.71c,nuclide_density,nu-fission,6.59e+02,2.05e+01
|
||||
1,U-235.71c,nuclide_density,total,-2.29e+03,2.59e+02
|
||||
1,U-235.71c,nuclide_density,absorption,-5.31e+01,5.44e+00
|
||||
1,U-235.71c,nuclide_density,fission,0.00e+00,0.00e+00
|
||||
1,U-235.71c,nuclide_density,nu-fission,0.00e+00,0.00e+00
|
||||
1,U-235.71c,nuclide_density,total,0.00e+00,0.00e+00
|
||||
1,U-235.71c,nuclide_density,absorption,0.00e+00,0.00e+00
|
||||
1,U-235.71c,nuclide_density,fission,0.00e+00,0.00e+00
|
||||
1,U-235.71c,nuclide_density,nu-fission,0.00e+00,0.00e+00
|
||||
3,,density,absorption,-3.29e-02,8.34e-02
|
||||
3,,density,absorption,1.21e-01,4.42e-02
|
||||
1,,density,absorption,1.51e-02,2.89e-03
|
||||
1,,density,absorption,-4.61e-03,2.30e-03
|
||||
1,O-16.71c,nuclide_density,absorption,2.87e-01,5.33e-01
|
||||
1,O-16.71c,nuclide_density,absorption,2.86e-01,3.59e-01
|
||||
1,U-235.71c,nuclide_density,absorption,1.14e+02,1.15e+01
|
||||
1,U-235.71c,nuclide_density,absorption,-5.10e+01,4.74e+00
|
||||
3,,density,nu-fission,4.24e-04,6.13e-02
|
||||
3,,density,nu-fission,2.40e-02,6.37e-02
|
||||
3,,density,nu-fission,0.00e+00,0.00e+00
|
||||
3,,density,nu-fission,0.00e+00,0.00e+00
|
||||
1,,density,nu-fission,-2.85e-02,2.57e-03
|
||||
1,,density,nu-fission,-6.16e-02,5.51e-03
|
||||
1,,density,nu-fission,0.00e+00,0.00e+00
|
||||
1,,density,nu-fission,0.00e+00,0.00e+00
|
||||
1,O-16.71c,nuclide_density,nu-fission,1.70e-01,2.18e-01
|
||||
1,O-16.71c,nuclide_density,nu-fission,6.30e-01,5.11e-01
|
||||
1,O-16.71c,nuclide_density,nu-fission,0.00e+00,0.00e+00
|
||||
1,O-16.71c,nuclide_density,nu-fission,0.00e+00,0.00e+00
|
||||
1,U-235.71c,nuclide_density,nu-fission,-2.00e+02,1.68e+01
|
||||
1,U-235.71c,nuclide_density,nu-fission,-4.76e+02,1.41e+01
|
||||
1,U-235.71c,nuclide_density,nu-fission,0.00e+00,0.00e+00
|
||||
1,U-235.71c,nuclide_density,nu-fission,0.00e+00,0.00e+00
|
||||
123
tests/test_diff_tally/test_diff_tally.py
Normal file
123
tests/test_diff_tally/test_diff_tally.py
Normal file
|
|
@ -0,0 +1,123 @@
|
|||
#!/usr/bin/env python
|
||||
|
||||
import glob
|
||||
import os
|
||||
import pandas as pd
|
||||
try:
|
||||
from StringIO import StringIO
|
||||
except:
|
||||
from io import StringIO
|
||||
import sys
|
||||
sys.path.insert(0, os.pardir)
|
||||
from testing_harness import PyAPITestHarness
|
||||
from openmc import Filter, Mesh, Tally, TalliesFile, Summary, StatePoint
|
||||
#from openmc.statepoint import StatePoint
|
||||
from openmc.source import Source
|
||||
from openmc.stats import Box
|
||||
|
||||
class DiffTallyTestHarness(PyAPITestHarness):
|
||||
def _build_inputs(self):
|
||||
# Build default materials/geometry
|
||||
self._input_set.build_default_materials_and_geometry()
|
||||
|
||||
# Set settings explicitly
|
||||
self._input_set.settings.batches = 5
|
||||
self._input_set.settings.inactive = 0
|
||||
self._input_set.settings.particles = 400
|
||||
self._input_set.settings.source = Source(space=Box(
|
||||
[-160, -160, -183], [160, 160, 183]))
|
||||
self._input_set.settings.output = {'summary':True}
|
||||
|
||||
self._input_set.tallies = TalliesFile()
|
||||
|
||||
filt_mats = Filter(type='material', bins=(1, 3))
|
||||
filt_eout = Filter(type='energyout', bins=(0.0, 1.0, 20.0))
|
||||
|
||||
def add_derivs(tally_list):
|
||||
assert len(tally_list) == 4
|
||||
# We want density derivatives for both water and fuel to get
|
||||
# coverage for both fissile and non-fissile materials.
|
||||
tally_list[0].diff_variable = 'density'
|
||||
tally_list[0].diff_material = 3
|
||||
tally_list[1].diff_variable = 'density'
|
||||
tally_list[1].diff_material = 1
|
||||
|
||||
# O-16 is a good nuclide to test against because it is present
|
||||
# in both water and fuel. Some routines need to recognize that they
|
||||
# have the perturbed nuclide but not the perturbed material.
|
||||
tally_list[2].diff_variable = 'nuclide_density'
|
||||
tally_list[2].diff_material = 1
|
||||
tally_list[2].diff_nuclide = 'O-16'
|
||||
|
||||
# A fissile nuclide, just for good measure.
|
||||
tally_list[3].diff_variable = 'nuclide_density'
|
||||
tally_list[3].diff_material = 1
|
||||
tally_list[3].diff_nuclide = 'U-235'
|
||||
|
||||
# Cover the flux score.
|
||||
tallies = [Tally() for i in range(4)]
|
||||
for t in tallies: t.add_score('flux')
|
||||
for t in tallies: t.add_filter(filt_mats)
|
||||
add_derivs(tallies)
|
||||
for t in tallies: self._input_set.tallies.add_tally(t)
|
||||
|
||||
# Cover supported scores with a collision estimator.
|
||||
tallies = [Tally() for i in range(4)]
|
||||
for t in tallies: t.add_score('total')
|
||||
for t in tallies: t.add_score('absorption')
|
||||
for t in tallies: t.add_score('fission')
|
||||
for t in tallies: t.add_score('nu-fission')
|
||||
for t in tallies: t.add_filter(filt_mats)
|
||||
for t in tallies: t.add_nuclide('total')
|
||||
for t in tallies: t.add_nuclide('U-235')
|
||||
add_derivs(tallies)
|
||||
for t in tallies: self._input_set.tallies.add_tally(t)
|
||||
|
||||
# Cover an analog estimator.
|
||||
tallies = [Tally() for i in range(4)]
|
||||
for t in tallies: t.add_score('absorption')
|
||||
for t in tallies: t.add_filter(filt_mats)
|
||||
for t in tallies: t.estimator = 'analog'
|
||||
add_derivs(tallies)
|
||||
for t in tallies: self._input_set.tallies.add_tally(t)
|
||||
|
||||
# And the special fission with energyout filter.
|
||||
tallies = [Tally() for i in range(4)]
|
||||
for t in tallies: t.add_score('nu-fission')
|
||||
for t in tallies: t.add_filter(filt_mats)
|
||||
for t in tallies: t.add_filter(filt_eout)
|
||||
add_derivs(tallies)
|
||||
for t in tallies: self._input_set.tallies.add_tally(t)
|
||||
|
||||
self._input_set.export()
|
||||
|
||||
def _get_results(self):
|
||||
#return super(DiffTallyTestHarness, self)._get_results(hash_output=True)
|
||||
# Read the statepoint and summary files.
|
||||
statepoint = glob.glob(os.path.join(os.getcwd(), self._sp_name))[0]
|
||||
sp = StatePoint(statepoint)
|
||||
su = Summary('summary.h5')
|
||||
sp.link_with_summary(su)
|
||||
|
||||
# Extract the tally data as a Pandas DataFrame.
|
||||
df = pd.DataFrame()
|
||||
for t in sp.tallies.values():
|
||||
df = df.append(t.get_pandas_dataframe(), ignore_index=True)
|
||||
|
||||
# Extract the relevant data as a CSV string.
|
||||
out = StringIO()
|
||||
cols = ('d_material', 'd_nuclide', 'd_variable', 'score', 'mean',
|
||||
'std. dev.')
|
||||
df.to_csv(out, columns=cols, index=False, float_format='%.2e')
|
||||
|
||||
return out.getvalue()
|
||||
|
||||
def _cleanup(self):
|
||||
super(DiffTallyTestHarness, self)._cleanup()
|
||||
f = os.path.join(os.getcwd(), 'tallies.xml')
|
||||
if os.path.exists(f): os.remove(f)
|
||||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = DiffTallyTestHarness('statepoint.5.*', True)
|
||||
harness.main()
|
||||
Loading…
Add table
Add a link
Reference in a new issue