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=origen

bounds {

    neutron="scale.rev13.xn200g47v7.1"

    gamma=[ 999I 2.0e7 1.0e4 ]

    }

build_lib("fuel_decay.f33") {

    neutron(1) {

        type=ENDF_ENERGY_DEPENDENT

        reaction_resource="origen.rev03.jeff200g"

        spectrum {

        type=MULTIGROUP

        flux=[ 0.0000e+00 0.0000e+00 0.0000e+00 0.0000e+00 0.0000e+00

               0.0000e+00 0.0000e+00 0.0000e+00 1.4590e-11 9.8338e-11

               2.0044e-09 1.6638e-09 2.0026e-09 5.6014e-09 8.2804e-09

               1.2502e-08 1.8118e-08 2.4896e-08 3.4461e-08 4.5239e-08

               5.9077e-08 7.7748e-08 1.0007e-07 1.2387e-07 1.6144e-07

               6.1808e-08 1.4026e-07 2.4358e-07 2.7675e-07 3.1704e-07

               3.8893e-07 4.3099e-07 5.0701e-07 5.4981e-07 1.2627e-06

               1.4516e-06 1.6336e-06 9.9224e-07 1.2066e-06 1.2742e-06

               1.3812e-06 1.5738e-06 1.5922e-06 1.1535e-06 3.2502e-07

               3.3926e-07 6.3136e-07 1.1845e-06 1.6635e-06 1.5837e-06

               1.5373e-06 1.4808e-06 1.8332e-06 1.8730e-06 1.7978e-06

               1.9273e-06 2.0350e-06 2.1472e-06 1.8088e-06 2.2527e-06

               2.5985e-06 2.4169e-06 3.8561e-06 1.3967e-06 2.6431e-06

               2.6498e-06 3.3745e-06 3.8597e-06 3.9963e-06 4.3505e-06

               4.6273e-06 4.8560e-06 4.9778e-06 5.2546e-06 4.7896e-06

               4.8597e-06 4.7416e-06 7.9593e-06 4.8376e-06 2.7996e-06

               3.2206e-06 7.7121e-06 8.9630e-06 1.2122e-06 4.3542e-07

               8.7195e-07 2.1051e-06 3.8413e-06 9.6862e-06 4.5092e-06

               4.3874e-06 4.4095e-06 4.3911e-06 3.8302e-06 3.9040e-06

               5.2878e-06 4.0295e-06 4.3394e-06 4.1328e-06 3.1417e-06

               4.0332e-06 5.2103e-06 4.4944e-06 4.1402e-06 3.9704e-06

               8.6457e-06 8.7268e-06 2.4409e-06 3.6631e-06 6.3247e-06

               4.8376e-06 1.0801e-05 4.1549e-06 6.8486e-06 6.7010e-06

               8.0184e-06 2.9797e-06 2.8926e-06 8.2988e-07 1.7092e-06

               3.3295e-06 1.3915e-06 1.1100e-06 2.9199e-06 4.6420e-06

               6.6715e-06 6.2582e-06 2.4550e-06 3.0099e-06 3.2402e-06

               3.3693e-06 2.8922e-06 1.4299e-06 9.7305e-07 8.6973e-07

               7.5719e-07 3.1321e-07 2.6151e-07 4.5793e-07 5.6605e-07

               1.2409e-06 9.0885e-07 5.4243e-07 3.9151e-07 2.5764e-07

               1.6564e-07 1.0347e-07 7.0258e-08 6.3283e-08 4.6531e-08

               3.7859e-08 2.8771e-08 2.6096e-08 2.1753e-08 1.6616e-08

               1.3428e-08 8.8523e-09 1.2347e-08 7.0442e-09 1.0701e-08

               8.8006e-09 8.4759e-09 6.7269e-09 5.5055e-09 9.5903e-09

               9.4612e-09 1.1321e-08 1.1232e-08 1.1601e-08 4.4428e-09

               3.8671e-09 7.3874e-10 7.1180e-10 7.4464e-10 2.5756e-09

               1.7461e-09 2.9435e-09 1.4498e-09 2.4431e-09 8.0995e-10

               2.0369e-09 1.0085e-09 7.6272e-10 8.8117e-10 9.8449e-10

               9.8597e-10 9.5386e-10 7.8782e-10 8.1881e-10 9.3652e-10

               5.1881e-10 2.1963e-10 1.7177e-10 1.0391e-10 4.0959e-11

               1.6705e-11 1.0620e-11 2.5682e-12 3.2930e-13 1.1616e-14]

       }

    }

}

case("fuel") {

  lib { file="fuel_decay.f33" }

  time { units=days start=0

         t=[ 1.0 7.0 30.0 90.0 180.0 365.0 730.0 1095.0 1460.0 1460.01 1461.0 1467.0 1490.0 1520.0 1550.0 1640.0 1825.0] }

  flux=[9r3.7e13 8r0.0 ]

  %  Gold in the treasure chest

  mat {units="ATOMS-PER-BARN-CM"

       volume=4.93235e+05

       iso=[   o16=4.637668e-02

               o17=1.766587e-05

               o18=9.530383e-05

              u234=3.537343e-05

              u235=4.684591e-03

              u238=1.852486e-02

             ]

      }

  neutron=yes

  gamma{

      sublib=ALL

      adjust_for_missing=no

      conserve_line_energy=no

      split_near_boundary=no

      continuum=yes

      immediate=yes

      spont=yes

      brem_medium=UO2

  }

  print {

      neutron{

          summary=yes

          spectra=yes

      }

      gamma{

          summary=yes

          spectra=yes

          principal_step=LAST

          principal_cutoff=5

          unbinned_warning=yes

      }

      cutoffs=[ all=1.0E-14 ]

      absfrac_sublib=ALL

      absfrac_step=LAST

      cutoff_step=AVERAGE

      rel_cutoff=yes

      fisrate=ABS

      kinf=yes

  }

  save {

      file="fuel_decay.f71"

      steps=ALL

  }

}

end

=opus

  title="Activation/Decay Source, Concentrations (grams)"

  data="fuel_decay.f71"

  units=grams

  typarams=nucl

  nrank=30

end

=opus

  title="Activation/Decay Source, Activities (curies)"

  data="fuel_decay.f71"

  units=curies

  typarams=elem

  nrank=30

end

=opus

  title="Activation/Decay Source, Neutron Spectrum (n/s)"

  data="fuel_decay.f71"

  typarams=nspectrum

  units=particles

  time=days

end

=opus

  title="Activation/Decay Source, Gamma Spectrum (p/s)"

  data="fuel_decay.f71"

  typarams=gspectrum

  units=particles

  time=days

end