diff --git a/examples/python/basic/build-xml.py b/examples/python/basic/build-xml.py
index 4dc1c72e0..f248c0a8a 100644
--- a/examples/python/basic/build-xml.py
+++ b/examples/python/basic/build-xml.py
@@ -15,21 +15,16 @@ particles = 10000
# Exporting to OpenMC materials.xml file
###############################################################################
-# Instantiate some Nuclides
-h1 = openmc.Nuclide('H1')
-o16 = openmc.Nuclide('O16')
-u235 = openmc.Nuclide('U235')
-
# Instantiate some Materials and register the appropriate Nuclides
moderator = openmc.Material(material_id=41, name='moderator')
moderator.set_density('g/cc', 1.0)
-moderator.add_nuclide(h1, 2.)
-moderator.add_nuclide(o16, 1.)
+moderator.add_element('H', 2.)
+moderator.add_element('O', 1.)
moderator.add_s_alpha_beta('c_H_in_H2O')
fuel = openmc.Material(material_id=40, name='fuel')
fuel.set_density('g/cc', 4.5)
-fuel.add_nuclide(u235, 1.)
+fuel.add_nuclide('U235', 1.)
# Instantiate a Materials collection and export to XML
materials_file = openmc.Materials([moderator, fuel])
diff --git a/examples/python/boxes/build-xml.py b/examples/python/boxes/build-xml.py
index 308019e7d..03e81b073 100644
--- a/examples/python/boxes/build-xml.py
+++ b/examples/python/boxes/build-xml.py
@@ -15,25 +15,19 @@ particles = 10000
# Exporting to OpenMC materials.xml File
###############################################################################
-# Instantiate some Nuclides
-h1 = openmc.Nuclide('H1')
-o16 = openmc.Nuclide('O16')
-u235 = openmc.Nuclide('U235')
-u238 = openmc.Nuclide('U238')
-
# Instantiate some Materials and register the appropriate Nuclides
fuel1 = openmc.Material(material_id=1, name='fuel')
fuel1.set_density('g/cc', 4.5)
-fuel1.add_nuclide(u235, 1.)
+fuel1.add_nuclide('U235', 1.)
fuel2 = openmc.Material(material_id=2, name='depleted fuel')
fuel2.set_density('g/cc', 4.5)
-fuel2.add_nuclide(u238, 1.)
+fuel2.add_nuclide('U238', 1.)
moderator = openmc.Material(material_id=3, name='moderator')
moderator.set_density('g/cc', 1.0)
-moderator.add_nuclide(h1, 2.)
-moderator.add_nuclide(o16, 1.)
+moderator.add_element('H', 2.)
+moderator.add_element('O', 1.)
moderator.add_s_alpha_beta('c_H_in_H2O')
# Instantiate a Materials collection and export to XML
diff --git a/examples/python/lattice/hexagonal/build-xml.py b/examples/python/lattice/hexagonal/build-xml.py
index 2b0bab38a..8d124930f 100644
--- a/examples/python/lattice/hexagonal/build-xml.py
+++ b/examples/python/lattice/hexagonal/build-xml.py
@@ -14,26 +14,20 @@ particles = 10000
# Exporting to OpenMC materials.xml File
###############################################################################
-# Instantiate some Nuclides
-h1 = openmc.Nuclide('H1')
-o16 = openmc.Nuclide('O16')
-u235 = openmc.Nuclide('U235')
-fe56 = openmc.Nuclide('Fe56')
-
# Instantiate some Materials and register the appropriate Nuclides
fuel = openmc.Material(material_id=1, name='fuel')
fuel.set_density('g/cc', 4.5)
-fuel.add_nuclide(u235, 1.)
+fuel.add_nuclide('U235', 1.)
moderator = openmc.Material(material_id=2, name='moderator')
moderator.set_density('g/cc', 1.0)
-moderator.add_nuclide(h1, 2.)
-moderator.add_nuclide(o16, 1.)
+moderator.add_element('H', 2.)
+moderator.add_element('O', 1.)
moderator.add_s_alpha_beta('c_H_in_H2O')
iron = openmc.Material(material_id=3, name='iron')
iron.set_density('g/cc', 7.9)
-iron.add_nuclide(fe56, 1.)
+iron.add_element('Fe', 1.)
# Instantiate a Materials collection and export to XML
materials_file = openmc.Materials([moderator, fuel, iron])
diff --git a/examples/python/lattice/nested/build-xml.py b/examples/python/lattice/nested/build-xml.py
index 2357d0bb7..363d0db90 100644
--- a/examples/python/lattice/nested/build-xml.py
+++ b/examples/python/lattice/nested/build-xml.py
@@ -14,20 +14,15 @@ particles = 10000
# Exporting to OpenMC materials.xml file
###############################################################################
-# Instantiate some Nuclides
-h1 = openmc.Nuclide('H1')
-o16 = openmc.Nuclide('O16')
-u235 = openmc.Nuclide('U235')
-
# Instantiate some Materials and register the appropriate Nuclides
fuel = openmc.Material(material_id=1, name='fuel')
fuel.set_density('g/cc', 4.5)
-fuel.add_nuclide(u235, 1.)
+fuel.add_nuclide('U235', 1.)
moderator = openmc.Material(material_id=2, name='moderator')
moderator.set_density('g/cc', 1.0)
-moderator.add_nuclide(h1, 2.)
-moderator.add_nuclide(o16, 1.)
+moderator.add_element('H', 2.)
+moderator.add_element('O', 1.)
moderator.add_s_alpha_beta('c_H_in_H2O')
# Instantiate a Materials collection and export to XML
diff --git a/examples/python/lattice/simple/build-xml.py b/examples/python/lattice/simple/build-xml.py
index 06139f091..354ce9cc4 100644
--- a/examples/python/lattice/simple/build-xml.py
+++ b/examples/python/lattice/simple/build-xml.py
@@ -14,20 +14,15 @@ particles = 10000
# Exporting to OpenMC materials.xml file
###############################################################################
-# Instantiate some Nuclides
-h1 = openmc.Nuclide('H1')
-o16 = openmc.Nuclide('O16')
-u235 = openmc.Nuclide('U235')
-
# Instantiate some Materials and register the appropriate Nuclides
fuel = openmc.Material(material_id=1, name='fuel')
fuel.set_density('g/cc', 4.5)
-fuel.add_nuclide(u235, 1.)
+fuel.add_nuclide('U235', 1.)
moderator = openmc.Material(material_id=2, name='moderator')
moderator.set_density('g/cc', 1.0)
-moderator.add_nuclide(h1, 2.)
-moderator.add_nuclide(o16, 1.)
+moderator.add_element('H', 2.)
+moderator.add_element('O', 1.)
moderator.add_s_alpha_beta('c_H_in_H2O')
# Instantiate a Materials collection and export to XML
diff --git a/examples/python/pincell/build-xml.py b/examples/python/pincell/build-xml.py
index cf01ba852..4d41a3126 100644
--- a/examples/python/pincell/build-xml.py
+++ b/examples/python/pincell/build-xml.py
@@ -14,86 +14,29 @@ particles = 1000
# Exporting to OpenMC materials.xml file
###############################################################################
-# Instantiate some Nuclides
-h1 = openmc.Nuclide('H1')
-h2 = openmc.Nuclide('H2')
-he4 = openmc.Nuclide('He4')
-b10 = openmc.Nuclide('B10')
-b11 = openmc.Nuclide('B11')
-o16 = openmc.Nuclide('O16')
-o17 = openmc.Nuclide('O17')
-cr50 = openmc.Nuclide('Cr50')
-cr52 = openmc.Nuclide('Cr52')
-cr53 = openmc.Nuclide('Cr53')
-cr54 = openmc.Nuclide('Cr54')
-fe54 = openmc.Nuclide('Fe54')
-fe56 = openmc.Nuclide('Fe56')
-fe57 = openmc.Nuclide('Fe57')
-fe58 = openmc.Nuclide('Fe58')
-zr90 = openmc.Nuclide('Zr90')
-zr91 = openmc.Nuclide('Zr91')
-zr92 = openmc.Nuclide('Zr92')
-zr94 = openmc.Nuclide('Zr94')
-zr96 = openmc.Nuclide('Zr96')
-sn112 = openmc.Nuclide('Sn112')
-sn114 = openmc.Nuclide('Sn114')
-sn115 = openmc.Nuclide('Sn115')
-sn116 = openmc.Nuclide('Sn116')
-sn117 = openmc.Nuclide('Sn117')
-sn118 = openmc.Nuclide('Sn118')
-sn119 = openmc.Nuclide('Sn119')
-sn120 = openmc.Nuclide('Sn120')
-sn122 = openmc.Nuclide('Sn122')
-sn124 = openmc.Nuclide('Sn124')
-u = openmc.Element('U')
-o = openmc.Element('O')
# Instantiate some Materials and register the appropriate Nuclides
uo2 = openmc.Material(material_id=1, name='UO2 fuel at 2.4% wt enrichment')
uo2.set_density('g/cm3', 10.29769)
-uo2.add_element(u, 1., enrichment=2.4)
-uo2.add_element(o, 2.)
+uo2.add_element('U', 1., enrichment=2.4)
+uo2.add_element('O', 2.)
helium = openmc.Material(material_id=2, name='Helium for gap')
helium.set_density('g/cm3', 0.001598)
-helium.add_nuclide(he4, 2.4044e-4)
+helium.add_element('He', 2.4044e-4)
zircaloy = openmc.Material(material_id=3, name='Zircaloy 4')
zircaloy.set_density('g/cm3', 6.55)
-zircaloy.add_nuclide(o16, 3.0743e-4)
-zircaloy.add_nuclide(o17, 7.4887e-7)
-zircaloy.add_nuclide(cr50, 3.2962e-6)
-zircaloy.add_nuclide(cr52, 6.3564e-5)
-zircaloy.add_nuclide(cr53, 7.2076e-6)
-zircaloy.add_nuclide(cr54, 1.7941e-6)
-zircaloy.add_nuclide(fe54, 8.6699e-6)
-zircaloy.add_nuclide(fe56, 1.3610e-4)
-zircaloy.add_nuclide(fe57, 3.1431e-6)
-zircaloy.add_nuclide(fe58, 4.1829e-7)
-zircaloy.add_nuclide(zr90, 2.1827e-2)
-zircaloy.add_nuclide(zr91, 4.7600e-3)
-zircaloy.add_nuclide(zr92, 7.2758e-3)
-zircaloy.add_nuclide(zr94, 7.3734e-3)
-zircaloy.add_nuclide(zr96, 1.1879e-3)
-zircaloy.add_nuclide(sn112, 4.6735e-6)
-zircaloy.add_nuclide(sn114, 3.1799e-6)
-zircaloy.add_nuclide(sn115, 1.6381e-6)
-zircaloy.add_nuclide(sn116, 7.0055e-5)
-zircaloy.add_nuclide(sn117, 3.7003e-5)
-zircaloy.add_nuclide(sn118, 1.1669e-4)
-zircaloy.add_nuclide(sn119, 4.1387e-5)
-zircaloy.add_nuclide(sn120, 1.5697e-4)
-zircaloy.add_nuclide(sn122, 2.2308e-5)
-zircaloy.add_nuclide(sn124, 2.7897e-5)
+zircaloy.add_element('Sn', 0.014 , 'wo')
+zircaloy.add_element('Fe', 0.00165, 'wo')
+zircaloy.add_element('Cr', 0.001 , 'wo')
+zircaloy.add_element('Zr', 0.98335, 'wo')
-borated_water = openmc.Material(material_id=4, name='Borated water at 975 ppm')
+borated_water = openmc.Material(material_id=4, name='Borated water')
borated_water.set_density('g/cm3', 0.740582)
-borated_water.add_nuclide(b10, 8.0042e-6)
-borated_water.add_nuclide(b11, 3.2218e-5)
-borated_water.add_nuclide(h1, 4.9457e-2)
-borated_water.add_nuclide(h2, 7.4196e-6)
-borated_water.add_nuclide(o16, 2.4672e-2)
-borated_water.add_nuclide(o17, 6.0099e-5)
+borated_water.add_element('B', 4.0e-5)
+borated_water.add_element('H', 5.0e-2)
+borated_water.add_element('O', 2.4e-2)
borated_water.add_s_alpha_beta('c_H_in_H2O')
# Instantiate a Materials collection and export to XML
diff --git a/examples/python/reflective/build-xml.py b/examples/python/reflective/build-xml.py
index af86e446a..09fa02626 100644
--- a/examples/python/reflective/build-xml.py
+++ b/examples/python/reflective/build-xml.py
@@ -15,13 +15,10 @@ particles = 10000
# Exporting to OpenMC materials.xml file
###############################################################################
-# Instantiate a Nuclides
-u235 = openmc.Nuclide('U235')
-
# Instantiate a Material and register the Nuclide
fuel = openmc.Material(material_id=1, name='fuel')
fuel.set_density('g/cc', 4.5)
-fuel.add_nuclide(u235, 1.)
+fuel.add_nuclide('U235', 1.)
# Instantiate a Materials collection and export to XML
materials_file = openmc.Materials([fuel])
diff --git a/openmc/settings.py b/openmc/settings.py
index cc3a1fbb0..e6a3f9e13 100644
--- a/openmc/settings.py
+++ b/openmc/settings.py
@@ -830,7 +830,7 @@ class Settings(object):
def _create_keff_trigger_subelement(self, run_mode_element):
if self._keff_trigger is not None:
- element = ET.SubElement(run_mode_subelement, "keff_trigger")
+ element = ET.SubElement(run_mode_element, "keff_trigger")
for key in self._keff_trigger:
subelement = ET.SubElement(element, key)
diff --git a/tests/test_mgxs_library_condense/inputs_true.dat b/tests/test_mgxs_library_condense/inputs_true.dat
index 2c9e622f8..ac3f32c4f 100644
--- a/tests/test_mgxs_library_condense/inputs_true.dat
+++ b/tests/test_mgxs_library_condense/inputs_true.dat
@@ -396,7 +396,7 @@
total
delayed-nu-fission
- analog
+ tracklength
@@ -404,7 +404,7 @@
total
decay-rate
- analog
+ tracklength
@@ -767,7 +767,7 @@
total
delayed-nu-fission
- analog
+ tracklength
@@ -775,7 +775,7 @@
total
decay-rate
- analog
+ tracklength
@@ -1138,7 +1138,7 @@
total
delayed-nu-fission
- analog
+ tracklength
@@ -1146,7 +1146,7 @@
total
decay-rate
- analog
+ tracklength
diff --git a/tests/test_mgxs_library_condense/results_true.dat b/tests/test_mgxs_library_condense/results_true.dat
index 6f29fbc4c..00cd27e1e 100644
--- a/tests/test_mgxs_library_condense/results_true.dat
+++ b/tests/test_mgxs_library_condense/results_true.dat
@@ -64,12 +64,12 @@
4 10000 5 1 total 0.001231 0.000105
5 10000 6 1 total 0.000512 0.000044
material delayedgroup group in nuclide mean std. dev.
-0 10000 1 1 total 0.000000 0.000000
-1 10000 2 1 total 0.032739 0.028454
-2 10000 3 1 total 0.120780 0.170809
-3 10000 4 1 total 0.302780 0.109110
-4 10000 5 1 total 0.000000 0.000000
-5 10000 6 1 total 0.000000 0.000000
+0 10000 1 1 total 0.013355 0.001207
+1 10000 2 1 total 0.032600 0.002866
+2 10000 3 1 total 0.121083 0.010442
+3 10000 4 1 total 0.305910 0.025627
+4 10000 5 1 total 0.861934 0.068282
+5 10000 6 1 total 2.895065 0.230223
material delayedgroup group in group out nuclide mean std. dev.
0 10000 1 1 1 total 0.000000 0.000000
1 10000 2 1 1 total 0.000384 0.000236
diff --git a/tests/test_mgxs_library_distribcell/inputs_true.dat b/tests/test_mgxs_library_distribcell/inputs_true.dat
index 682f598f7..fd0401527 100644
--- a/tests/test_mgxs_library_distribcell/inputs_true.dat
+++ b/tests/test_mgxs_library_distribcell/inputs_true.dat
@@ -423,7 +423,7 @@
total
delayed-nu-fission
- analog
+ tracklength
@@ -431,7 +431,7 @@
total
decay-rate
- analog
+ tracklength
diff --git a/tests/test_mgxs_library_distribcell/results_true.dat b/tests/test_mgxs_library_distribcell/results_true.dat
index 905a55815..52d668e0b 100644
--- a/tests/test_mgxs_library_distribcell/results_true.dat
+++ b/tests/test_mgxs_library_distribcell/results_true.dat
@@ -64,12 +64,12 @@
4 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 5 1 total 0.001210 0.000058
5 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 6 1 total 0.000504 0.000024
sum(distribcell) delayedgroup group in nuclide mean std. dev.
-0 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total 0.000000 0.000000
-1 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 2 1 total 0.032739 0.046300
-2 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 3 1 total 0.120780 0.170809
-3 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 4 1 total 0.000000 0.000000
-4 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 5 1 total 0.000000 0.000000
-5 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 6 1 total 2.853000 4.034751
+0 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total 0.013353 0.000686
+1 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 2 1 total 0.032613 0.001627
+2 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 3 1 total 0.121054 0.005911
+3 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 4 1 total 0.305627 0.014428
+4 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 5 1 total 0.860892 0.037879
+5 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 6 1 total 2.891521 0.127879
sum(distribcell) delayedgroup group in group out nuclide mean std. dev.
0 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 1 total 0.000000 0.000000
1 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 2 1 1 total 0.000175 0.000175
diff --git a/tests/test_mgxs_library_hdf5/inputs_true.dat b/tests/test_mgxs_library_hdf5/inputs_true.dat
index 2c9e622f8..ac3f32c4f 100644
--- a/tests/test_mgxs_library_hdf5/inputs_true.dat
+++ b/tests/test_mgxs_library_hdf5/inputs_true.dat
@@ -396,7 +396,7 @@
total
delayed-nu-fission
- analog
+ tracklength
@@ -404,7 +404,7 @@
total
decay-rate
- analog
+ tracklength
@@ -767,7 +767,7 @@
total
delayed-nu-fission
- analog
+ tracklength
@@ -775,7 +775,7 @@
total
decay-rate
- analog
+ tracklength
@@ -1138,7 +1138,7 @@
total
delayed-nu-fission
- analog
+ tracklength
@@ -1146,7 +1146,7 @@
total
decay-rate
- analog
+ tracklength
diff --git a/tests/test_mgxs_library_hdf5/results_true.dat b/tests/test_mgxs_library_hdf5/results_true.dat
index d491e72ba..3f276cf5a 100644
--- a/tests/test_mgxs_library_hdf5/results_true.dat
+++ b/tests/test_mgxs_library_hdf5/results_true.dat
@@ -117,18 +117,18 @@ domain=10000 type=beta
[1.82980497e-04 4.50738567e-04]
[7.48899920e-05 1.88812772e-04]]
domain=10000 type=decay-rate
-[[0.00000000e+00 0.00000000e+00]
- [0.00000000e+00 3.27390000e-02]
- [0.00000000e+00 1.20780000e-01]
- [0.00000000e+00 3.02780000e-01]
- [0.00000000e+00 0.00000000e+00]
- [0.00000000e+00 0.00000000e+00]]
-[[0.00000000e+00 0.00000000e+00]
- [0.00000000e+00 2.84543737e-02]
- [0.00000000e+00 1.70808714e-01]
- [0.00000000e+00 1.09109511e-01]
- [0.00000000e+00 0.00000000e+00]
- [0.00000000e+00 0.00000000e+00]]
+[[1.34450193e-02 1.33360001e-02]
+ [3.20638662e-02 3.27389978e-02]
+ [1.22136025e-01 1.20780007e-01]
+ [3.15269337e-01 3.02780066e-01]
+ [8.89232590e-01 8.49490287e-01]
+ [2.98940410e+00 2.85300088e+00]]
+[[1.08439397e-03 1.44623816e-03]
+ [2.65794939e-03 3.55041884e-03]
+ [1.02955008e-02 1.30981285e-02]
+ [2.71748525e-02 3.28353351e-02]
+ [7.93682876e-02 9.21239479e-02]
+ [2.66253276e-01 3.09396954e-01]]
domain=10000 type=delayed-nu-fission matrix
[[[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]]
diff --git a/tests/test_mgxs_library_mesh/inputs_true.dat b/tests/test_mgxs_library_mesh/inputs_true.dat
index 675251ad5..07b2076d7 100644
--- a/tests/test_mgxs_library_mesh/inputs_true.dat
+++ b/tests/test_mgxs_library_mesh/inputs_true.dat
@@ -660,7 +660,7 @@
total
delayed-nu-fission
- analog
+ tracklength
@@ -668,7 +668,7 @@
total
decay-rate
- analog
+ tracklength
diff --git a/tests/test_mgxs_library_mesh/results_true.dat b/tests/test_mgxs_library_mesh/results_true.dat
index b4681d25c..df4dcd340 100644
--- a/tests/test_mgxs_library_mesh/results_true.dat
+++ b/tests/test_mgxs_library_mesh/results_true.dat
@@ -214,32 +214,32 @@
21 2 2 1 4 1 total 0.002675 0.000783
22 2 2 1 5 1 total 0.001199 0.000341
23 2 2 1 6 1 total 0.000499 0.000142
- mesh 1 delayedgroup group in nuclide mean std. dev.
- x y z
-0 1 1 1 1 1 total 0.00000 0.00000
-1 1 1 1 2 1 total 0.00000 0.00000
-2 1 1 1 3 1 total 0.00000 0.00000
-3 1 1 1 4 1 total 0.00000 0.00000
-4 1 1 1 5 1 total 0.84949 1.20136
-5 1 1 1 6 1 total 0.00000 0.00000
-6 1 2 1 1 1 total 0.00000 0.00000
-7 1 2 1 2 1 total 0.00000 0.00000
-8 1 2 1 3 1 total 0.00000 0.00000
-9 1 2 1 4 1 total 0.00000 0.00000
-10 1 2 1 5 1 total 0.00000 0.00000
-11 1 2 1 6 1 total 0.00000 0.00000
-12 2 1 1 1 1 total 0.00000 0.00000
-13 2 1 1 2 1 total 0.00000 0.00000
-14 2 1 1 3 1 total 0.00000 0.00000
-15 2 1 1 4 1 total 0.00000 0.00000
-16 2 1 1 5 1 total 0.00000 0.00000
-17 2 1 1 6 1 total 0.00000 0.00000
-18 2 2 1 1 1 total 0.00000 0.00000
-19 2 2 1 2 1 total 0.00000 0.00000
-20 2 2 1 3 1 total 0.00000 0.00000
-21 2 2 1 4 1 total 0.00000 0.00000
-22 2 2 1 5 1 total 0.00000 0.00000
-23 2 2 1 6 1 total 0.00000 0.00000
+ mesh 1 delayedgroup group in nuclide mean std. dev.
+ x y z
+0 1 1 1 1 1 total 0.013362 0.003586
+1 1 1 1 2 1 total 0.032554 0.008644
+2 1 1 1 3 1 total 0.121179 0.031941
+3 1 1 1 4 1 total 0.306858 0.079970
+4 1 1 1 5 1 total 0.865303 0.220416
+5 1 1 1 6 1 total 2.906554 0.741587
+6 1 2 1 1 1 total 0.013362 0.004521
+7 1 2 1 2 1 total 0.032556 0.011045
+8 1 2 1 3 1 total 0.121174 0.041226
+9 1 2 1 4 1 total 0.306816 0.104995
+10 1 2 1 5 1 total 0.865155 0.301124
+11 1 2 1 6 1 total 2.906049 1.010025
+12 2 1 1 1 1 total 0.013353 0.002006
+13 2 1 1 2 1 total 0.032614 0.004677
+14 2 1 1 3 1 total 0.121052 0.016785
+15 2 1 1 4 1 total 0.305600 0.040199
+16 2 1 1 5 1 total 0.860792 0.101713
+17 2 1 1 6 1 total 2.891182 0.344217
+18 2 2 1 1 1 total 0.013356 0.004047
+19 2 2 1 2 1 total 0.032596 0.009453
+20 2 2 1 3 1 total 0.121091 0.034091
+21 2 2 1 4 1 total 0.305990 0.082530
+22 2 2 1 5 1 total 0.862223 0.216936
+23 2 2 1 6 1 total 2.896051 0.731528
mesh 1 delayedgroup group in group out nuclide mean std. dev.
x y z
0 1 1 1 1 1 1 total 0.000000 0.000000
diff --git a/tests/test_mgxs_library_no_nuclides/inputs_true.dat b/tests/test_mgxs_library_no_nuclides/inputs_true.dat
index 2c9e622f8..ac3f32c4f 100644
--- a/tests/test_mgxs_library_no_nuclides/inputs_true.dat
+++ b/tests/test_mgxs_library_no_nuclides/inputs_true.dat
@@ -396,7 +396,7 @@
total
delayed-nu-fission
- analog
+ tracklength
@@ -404,7 +404,7 @@
total
decay-rate
- analog
+ tracklength
@@ -767,7 +767,7 @@
total
delayed-nu-fission
- analog
+ tracklength
@@ -775,7 +775,7 @@
total
decay-rate
- analog
+ tracklength
@@ -1138,7 +1138,7 @@
total
delayed-nu-fission
- analog
+ tracklength
@@ -1146,7 +1146,7 @@
total
decay-rate
- analog
+ tracklength
diff --git a/tests/test_mgxs_library_no_nuclides/results_true.dat b/tests/test_mgxs_library_no_nuclides/results_true.dat
index fac47af46..b4a83befd 100644
--- a/tests/test_mgxs_library_no_nuclides/results_true.dat
+++ b/tests/test_mgxs_library_no_nuclides/results_true.dat
@@ -129,18 +129,18 @@
8 10000 5 2 total 0.004684 0.000451
10 10000 6 2 total 0.001962 0.000189
material delayedgroup group in nuclide mean std. dev.
-1 10000 1 1 total 0.000000 0.000000
-3 10000 2 1 total 0.000000 0.000000
-5 10000 3 1 total 0.000000 0.000000
-7 10000 4 1 total 0.000000 0.000000
-9 10000 5 1 total 0.000000 0.000000
-11 10000 6 1 total 0.000000 0.000000
-0 10000 1 2 total 0.000000 0.000000
-2 10000 2 2 total 0.032739 0.028454
-4 10000 3 2 total 0.120780 0.170809
-6 10000 4 2 total 0.302780 0.109110
-8 10000 5 2 total 0.000000 0.000000
-10 10000 6 2 total 0.000000 0.000000
+1 10000 1 1 total 0.013445 0.001084
+3 10000 2 1 total 0.032064 0.002658
+5 10000 3 1 total 0.122136 0.010296
+7 10000 4 1 total 0.315269 0.027175
+9 10000 5 1 total 0.889233 0.079368
+11 10000 6 1 total 2.989404 0.266253
+0 10000 1 2 total 0.013336 0.001446
+2 10000 2 2 total 0.032739 0.003550
+4 10000 3 2 total 0.120780 0.013098
+6 10000 4 2 total 0.302780 0.032835
+8 10000 5 2 total 0.849490 0.092124
+10 10000 6 2 total 2.853001 0.309397
material delayedgroup group in group out nuclide mean std. dev.
3 10000 1 1 1 total 0.000000 0.000000
7 10000 2 1 1 total 0.000000 0.000000