new_contents: import openmc
  import pytest
  
  
  @pytest.fixture
  def th232_model():
      # URR boundaries for Th232
      e_min, e_max = 4000.0, 100000.0
  
      model = openmc.model.Model()
      th232 = openmc.Material()
      th232.add_nuclide('Th232', 1.0)
  
      surf = openmc.Sphere(r=100.0, boundary_type='reflective')
      cell = openmc.Cell(fill=th232, region=-surf)
      model.geometry = openmc.Geometry([cell])
  
      model.settings.particles = 100
      model.settings.batches = 10
      model.settings.run_mode = 'fixed source'
      energies = openmc.stats.Uniform(e_min, e_max)
      model.settings.source = openmc.Source(energy=energies)
  
      tally = openmc.Tally(name='rates')
      tally.filters = [openmc.EnergyFilter([e_min, e_max])]
      tally.scores = ['(n,gamma)', 'absorption', 'fission']
      model.tallies.append(tally)
      return model
  
  
  def test_urr_capture(run_in_tmpdir, th232_model):
      # Export and run model
      th232_model.export_to_xml()
      openmc.run()
  
      # Get reaction rates from tally
      with openmc.StatePoint('statepoint.10.h5') as sp:
          t = sp.get_tally(name='rates')
          ngamma, absorption, fission = t.mean.flatten()
  
      # In URR, the (n,gamma) rate should be equal to absorption - fission
      assert ngamma == pytest.approx(absorption - fission)
  
subject: Add (currently failing) test with URR (n,gamma) reaction rate check