Merge branch 'develop' into chain-fission-yields

docs/source/developers.rst

@@ -1,28 +0,0 @@
-.. _developers:
-
-================
-Development Team
-================
-
-The following people have contributed to development of the OpenMC Monte Carlo
-code:
-
-* `Paul Romano <https://github.com/paulromano>`_
-* `Bryan Herman <https://github.com/bhermanmit>`_
-* `Nick Horelik <https://github.com/nhorelik>`_
-* `Adam Nelson <https://github.com/nelsonag>`_
-* `Jon Walsh <https://github.com/walshjon>`_
-* `Sterling Harper <https://github.com/smharper>`_
-* `Will Boyd <https://github.com/wbinventor>`_
-* `Samuel Shaner <https://github.com/samuelshaner>`_
-* `Jingang Liang <https://github.com/liangjg>`_
-* `Colin Josey <https://github.com/cjosey>`_
-* `Amanda Lund <https://github.com/amandalund>`_
-* `Guillaume Giudicelli <https://github.com/giudgiud>`_
-* `Isaac Meyer <https://github.com/icmeyer>`_
-* `Patrick Shriwise <https://github.com/pshriwise>`_
-* `Shikhar Kumar <https://github.com/shikhar413>`_
-* `Andrew Davis <https://github.com/makeclean>`_
-* `Benoit Forget <http://web.mit.edu/nse/people/faculty/forget.html>`_
-* `Kord Smith <http://web.mit.edu/nse/people/faculty/smith.html>`_
-* `Andrew Siegel <http://www.mcs.anl.gov/person/andrew-siegel>`_

docs/source/index.rst

@@ -44,4 +44,3 @@ list <https://groups.google.com/forum/?fromgroups=#!forum/openmc-users>`_.
     io_formats/index
     publications
     license
-    developers

docs/source/license.rst

@@ -4,7 +4,7 @@
 License Agreement
 =================
 
-Copyright © 2011-2018 Massachusetts Institute of Technology and OpenMC contributors
+Copyright © 2011-2019 Massachusetts Institute of Technology and OpenMC contributors
 
 Permission is hereby granted, free of charge, to any person obtaining a copy of
 this software and associated documentation files (the "Software"), to deal in

docs/source/publications.rst

@@ -57,6 +57,9 @@ Benchmarking
 Coupling and Multi-physics
 --------------------------
 
+- Miriam A. Kreher, Benoit Forget, and Kord Smith, "Single-Batch Monte Carlo
+  Multiphysics Coupling," *Proc. M&C*, Portland, Oregon, Aug. 25-29 (2019).
+
 - Ze-Long Zhao, Yongwei Yang, and Shuang Hong, "`Application of FLUKA and OpenMC
   in coupled physics calculation of target and subcritical reactor for ADS
   <https://doi.org/10.1007/s41365-018-0539-1>`_," *Nucl. Sci. Tech.*, **30**: 10
@@ -113,6 +116,10 @@ Coupling and Multi-physics
 Geometry and Visualization
 --------------------------
 
+- Sterling Harper, Paul Romano, Benoit Forget, and Kord Smith, "Efficient
+  dynamic threadsafe neighbor lists for Monte Carlo ray tracing," *Proc. M&C*,
+  Portland, Oregon, Aug. 25-29 (2019).
+
 - Jin-Yang Li, Long Gu, Hu-Shan Xu, Nadezha Korepanova, Rui Yu, Yan-Lei Zhu, and
   Chang-Ping Qin, "`CAD modeling study on FLUKA and OpenMC for accelerator
   driven system simulation <https://doi.org/10.1016/j.anucene.2017.12.050>`_",
@@ -303,6 +310,11 @@ Multigroup Cross Section Generation
 Doppler Broadening
 ------------------
 
+- Jonathan A. Walsh, Benoit Forget, Kord S. Smith, and Forrest B. Brown,
+  "`On-the-fly Doppler broadening of unresolved resonance region cross sections
+  <https://doi.org/10.1016/j.pnucene.2017.05.032>`_," *Prog. Nucl. Energy*,
+  **101**, 444-460 (2017).
+
 - Colin Josey, Pablo Ducru, Benoit Forget, and Kord Smith, "`Windowed multipole
   for cross section Doppler broadening
   <https://doi.org/10.1016/j.jcp.2015.08.013>`_," *J. Comput. Phys.*, **307**,
@@ -313,6 +325,12 @@ Doppler Broadening
   via Probability Band Interpolation," *Proc. PHYSOR*, Sun Valley, Idaho, May
   1-5, 2016.
 
+- Jonathan A. Walsh, Benoit Forget, Kord S. Smith, Brian C. Kiedrowski, and
+  Forrest B. Brown, "`Direct, on-the-fly calculation of unresolved resonance
+  region cross sections in Monte Carlo simulations
+  <http://hdl.handle.net/1721.1/108644>`_," *Proc. Joint Int. Conf. M&C+SNA+MC*,
+  Nashville, Tennessee, Apr. 19--23 (2015).
+
 - Colin Josey, Benoit Forget, and Kord Smith, "`Windowed multipole sensitivity
   to target accuracy of the optimization procedure
   <https://doi.org/10.1080/00223131.2015.1035353>`_,"
@@ -366,11 +384,6 @@ Nuclear Data
   <https://doi.org/10.1016/j.cpc.2015.05.025>`_", *Comput. Phys. Commun.*,
   **196**, 134-142 (2015).
 
-- Jonathan A. Walsh, Benoit Forget, Kord S. Smith, Brian C. Kiedrowski, and
-  Forrest B. Brown, "Direct, on-the-fly calculation of unresolved resonance
-  region cross sections in Monte Carlo simulations," *Proc. Joint
-  Int. Conf. M&C+SNA+MC*, Nashville, Tennessee, Apr. 19--23 (2015).
-
 - Amanda L. Lund, Andrew R. Siegel, Benoit Forget, Colin Josey, and
   Paul K. Romano, "Using fractional cascading to accelerate cross section
   lookups in Monte Carlo particle transport calculations," *Proc. Joint
@@ -481,6 +494,10 @@ Parallelism
 Depletion
 ---------
 
+- Jose L. Salcedo-Perez, Benoit Forget, Kord Smith, and Paul Romano, "Hybrid
+  tallies to improve performance in depletion Monte Carlo simulations," *Proc.
+  M&C*, Aug. 25-29 (2019).
+
 - Zhao-Qing Liu, Ze-Long Zhao, Yong-Wei Yang, Yu-Cui Gao, Hai-Yan Meng, and
   Qing-Yu Gao, "`Development and validation of depletion code system IMPC-Burnup
   for ADS <https://doi.org/10.1007/s41365-019-0560-z>`_," *Nucl. Sci. Tech.*,

docs/source/usersguide/scripts.rst

@@ -106,6 +106,37 @@ Compton profile data using an existing data library from `Geant4
 <http://geant4.cern.ch/>`_. Note that OpenMC includes this data file by default
 so it should not be necessary in practice to generate it yourself.
 
+
+.. _scripts_depletion_chain:
+
+-------------------------------
+``openmc-make-depletion-chain``
+-------------------------------
+
+This script generates a depletion chain file called ``chain_endfb71.xml``
+using ENDF/B-VII.1 nuclear data. If the :envvar:`OPENMC_ENDF_DATA` variable
+is not set, and ``"neutron"``, ``"decay"``, ``"nfy"`` directories
+do not exist, then ENDF/B-VII.1 data will be downloaded.
+
+.. _scripts_depletion_chain_casl:
+
+------------------------------------
+``openmc-make-depletion-chain-casl``
+------------------------------------
+
+This script generates a depletion chain called ``chain_casl.xml``
+using ENDF/B-VII.1 nuclear data for a simplified chain.
+The nuclides were chosen by CASL-ORIGEN, which can be found in
+Appendix A of Kang Seog Kim, `"Specification for the VERA Depletion
+Benchmark Suite" <https://doi.org/10.2172/1256820>`_,
+CASL-U-2015-1014-000, Rev. 0, ORNL/TM-2016/53, 2016.
+``Te129`` has been added into this chain due to its link to
+``I129`` production.
+
+If the :envvar:`OPENMC_ENDF_DATA` variable is not set,
+and ``"neutron"``, ``"decay"``, ``"nfy"`` directories
+to not exist, then ENDF/B-VII.1 data will be downloaded.
+
 .. _scripts_stopping:
 
 -------------------------------

include/openmc/nuclide.h

@@ -126,6 +126,12 @@ namespace data {
 extern std::array<double, 2> energy_min;
 extern std::array<double, 2> energy_max;
 
+//! Minimum temperature in [K] that nuclide data is available at
+extern double temperature_min;
+
+//! Maximum temperature in [K] that nuclide data is available at
+extern double temperature_max;
+
 extern std::vector<std::unique_ptr<Nuclide>> nuclides;
 extern std::unordered_map<std::string, int> nuclide_map;
 

man/man1/openmc.1

@@ -54,7 +54,7 @@ Indicates the default path to an HDF5 file that contains multi-group cross
 section libraries if the user has not specified the <cross_sections> tag in
 .I materials.xml\fP.
 .SH LICENSE
-Copyright \(co 2011-2018 Massachusetts Institute of Technology and OpenMC
+Copyright \(co 2011-2019 Massachusetts Institute of Technology and OpenMC
 contributors.
 .PP
 Permission is hereby granted, free of charge, to any person obtaining a copy of

openmc/deplete/chain.py

@@ -10,9 +10,10 @@ import math
 import re
 from collections import OrderedDict, defaultdict
 from collections.abc import Mapping, Iterable
+from numbers import Real
 from warnings import warn
 
-from openmc.checkvalue import check_type, check_less_than
+from openmc.checkvalue import check_type, check_less_than, check_greater_than
 from openmc.data import gnd_name, zam
 from .nuclide import FissionYieldDistribution
 
@@ -666,3 +667,53 @@ class Chain(object):
                 yields = [yields]
             check_type("fission_yields", yields, Iterable, Mapping)
         self._fission_yields = yields
+    def validate(self, strict=True, quiet=False, tolerance=1e-4):
+        """Search for possible inconsistencies
+
+        The following checks are performed for all nuclides present:
+
+            1) For all non-fission reactions, does the sum of branching
+               ratios equal about one?
+            2) For fission reactions, does the sum of fission yield
+               fractions equal about two?
+
+        Parameters
+        ----------
+        strict : bool, optional
+            Raise exceptions at the first inconsistency if true.
+            Otherwise mark a warning
+        quiet : bool, optional
+            Flag to suppress warnings and return immediately at
+            the first inconsistency. Used only if
+            ``strict`` does not evaluate to ``True``.
+        tolerance : float, optional
+            Absolute tolerance for comparisons. Used to compare computed
+            value ``x`` to intended value ``y`` as::
+
+                valid = (y - tolerance <= x <= y + tolerance)
+
+        Returns
+        -------
+        valid : bool
+            True if no inconsistencies were found
+
+        Raises
+        ------
+        ValueError
+            If ``strict`` evaluates to ``True`` and an inconistency was
+            found
+
+        See Also
+        --------
+        openmc.deplete.Nuclide.validate
+        """
+        check_type("tolerance", tolerance, Real)
+        check_greater_than("tolerance", tolerance, 0.0, True)
+        valid = True
+        # Sort through nuclides by name
+        for name in sorted(self.nuclide_dict):
+            stat = self[name].validate(strict, quiet, tolerance)
+            if quiet and not stat:
+                return stat
+            valid = valid and stat
+        return valid

openmc/deplete/nuclide.py

@@ -3,9 +3,9 @@
 Contains the per-nuclide components of a depletion chain.
 """
 
-from collections import namedtuple
 from collections.abc import Mapping
-
+from collections import namedtuple, defaultdict
+from warnings import warn
 try:
     import lxml.etree as ET
 except ImportError:
@@ -241,6 +241,103 @@ class Nuclide(object):
 
         return elem
 
+    def validate(self, strict=True, quiet=False, tolerance=1e-4):
+        """Search for possible inconsistencies
+
+        The following checks are performed:
+
+            1) for all non-fission reactions and decay modes,
+               does the sum of branching ratios equal about one?
+            2) for fission reactions, does the sum of fission yield
+               fractions equal about two?
+
+        Parameters
+        ----------
+        strict : bool, optional
+            Raise exceptions at the first inconsistency if true.
+            Otherwise mark a warning
+        quiet : bool, optional
+            Flag to suppress warnings and return immediately at
+            the first inconsistency. Used only if
+            ``strict`` does not evaluate to ``True``.
+        tolerance : float, optional
+            Absolute tolerance for comparisons. Used to compare computed
+            value ``x`` to intended value ``y`` as::
+
+                valid = (y - tolerance <= x <= y + tolerance)
+
+        Returns
+        -------
+        valid : bool
+            True if no inconsistencies were found
+
+        Raises
+        ------
+        ValueError
+            If ``strict`` evaluates to ``True`` and an inconistency was
+            found
+
+        See Also
+        --------
+        openmc.deplete.Chain.validate
+        """
+
+        msg_func = ("Nuclide {name} has {prop} that sum to {actual} "
+                    "instead of {expected} +/- {tol:7.4e}").format
+        valid = True
+
+        # check decay modes
+        if self.decay_modes:
+            sum_br = sum(m.branching_ratio for m in self.decay_modes)
+            stat = 1.0 - tolerance <= sum_br <= 1.0 + tolerance
+            if not stat:
+                msg = msg_func(
+                    name=self.name, actual=sum_br, expected=1.0, tol=tolerance,
+                    prop="decay mode branch ratios")
+                if strict:
+                    raise ValueError(msg)
+                elif quiet:
+                    return False
+                warn(msg)
+                valid = False
+
+        if self.reactions:
+            type_map = defaultdict(set)
+            for reaction in self.reactions:
+                type_map[reaction.type].add(reaction)
+            for rxn_type, reactions in type_map.items():
+                sum_rxn = sum(rx.branching_ratio for rx in reactions)
+                stat = 1.0 - tolerance <= sum_rxn <= 1.0 + tolerance
+                if stat:
+                    continue
+                msg = msg_func(
+                    name=self.name, actual=sum_br, expected=1.0, tol=tolerance,
+                    prop="{} reaction branch ratios".format(rxn_type))
+                if strict:
+                    raise ValueError(msg)
+                elif quiet:
+                    return False
+                warn(msg)
+                valid = False
+
+        if self.yield_data:
+            for energy, yield_list in self.yield_data.items():
+                sum_yield = sum(y[1] for y in yield_list)
+                stat = 2.0 - tolerance <= sum_yield <= 2.0 + tolerance
+                if stat:
+                    continue
+                msg = msg_func(
+                    name=self.name, actual=sum_yield,
+                    expected=2.0, tol=tolerance,
+                    prop="fission yields (E = {:7.4e} eV)".format(energy))
+                if strict:
+                    raise ValueError(msg)
+                elif quiet:
+                    return False
+                warn(msg)
+                valid = False
+
+        return valid
 
 class FissionYieldDistribution(Mapping):
     """Energy-dependent fission product yields for a single nuclide

scripts/casl_chain.py

@@ -6,6 +6,8 @@
 # Note 32 of the 255 nuclides appeare twice as they are both activation
 # nuclides (category 1) and fission product nuclides (category 3).
 
+# Te129 has been added due to it's link to I129 production.
+
 CASL_CHAIN = {
     # Nuclide: (Stable, CAT, IFPY, Special yield treatment)
     # Stable: True if nuclide has no decay reactions
@@ -187,6 +189,7 @@ CASL_CHAIN = {
     'Sb127': (False, 3, 2, None),
     'Te127': (False, 3, -1, None),
     'Te127_m1': (False, 3, -1, None),
+    'Te129': (False, 3, 1, None),
     'Te129_m1': (False, 3, 2, None),
     'Te132': (False, 3, 2, None),
     'I127': (True, 3, 1, None),

scripts/openmc-make-depletion-chain

@@ -1,7 +1,7 @@
 #!/usr/bin/env python3
 
-import glob
 import os
+from pathlib import Path
 from zipfile import ZipFile
 
 from openmc._utils import download
@@ -15,15 +15,28 @@ URLS = [
 ]
 
 def main():
-    for url in URLS:
-        basename = download(url)
-        with ZipFile(basename, 'r') as zf:
-            print('Extracting {}...'.format(basename))
-            zf.extractall()
+    endf_dir = os.environ.get("OPENMC_ENDF_DATA")
+    if endf_dir is not None:
+        endf_dir = Path(endf_dir)
+    elif all(os.path.isdir(lib) for lib in ("neutrons", "decay", "nfy")):
+        endf_dir = Path(".")
+    else:
+        for url in URLS:
+            basename = download(url)
+            with ZipFile(basename, 'r') as zf:
+                print('Extracting {}...'.format(basename))
+                zf.extractall()
+        endf_dir = Path(".")
 
-    decay_files = glob.glob(os.path.join('decay', '*.endf'))
-    nfy_files = glob.glob(os.path.join('nfy', '*.endf'))
-    neutron_files = glob.glob(os.path.join('neutrons', '*.endf'))
+    decay_files = tuple((endf_dir / "decay").glob("*endf"))
+    neutron_files = tuple((endf_dir / "neutrons").glob("*endf"))
+    nfy_files = tuple((endf_dir / "nfy").glob("*endf"))
+
+    # check files exist
+    for flist, ftype in [(decay_files, "decay"), (neutron_files, "neutron"),
+                         (nfy_files, "neutron fission product yield")]:
+        if not flist:
+            raise IOError("No {} endf files found in {}".format(ftype, endf_dir))
 
     chain = openmc.deplete.Chain.from_endf(decay_files, nfy_files, neutron_files)
     chain.export_to_xml('chain_endfb71.xml')

src/cell.cpp

@@ -16,6 +16,7 @@
 #include "openmc/hdf5_interface.h"
 #include "openmc/lattice.h"
 #include "openmc/material.h"
+#include "openmc/nuclide.h"
 #include "openmc/settings.h"
 #include "openmc/surface.h"
 #include "openmc/xml_interface.h"
@@ -244,6 +245,16 @@ Cell::temperature(int32_t instance) const
 void
 Cell::set_temperature(double T, int32_t instance)
 {
+  if (settings::temperature_method == TEMPERATURE_INTERPOLATION) {
+    if (T < data::temperature_min) {
+      throw std::runtime_error{"Temperature is below minimum temperature at "
+        "which data is available."};
+    } else if (T > data::temperature_max) {
+      throw std::runtime_error{"Temperature is above maximum temperature at "
+        "which data is available."};
+    }
+  }
+
   if (instance >= 0) {
     sqrtkT_.at(instance) = std::sqrt(K_BOLTZMANN * T);
   } else {
@@ -1057,7 +1068,6 @@ openmc_cell_set_fill(int32_t index, int type, int32_t n,
   return 0;
 }
 
-//TODO: make sure data is loaded for this temperature
 extern "C" int
 openmc_cell_set_temperature(int32_t index, double T, const int32_t* instance)
 {

src/cross_sections.cpp

@@ -357,6 +357,12 @@ read_ce_cross_sections(const std::vector<std::vector<double>>& nuc_temps,
     }
   }
 
+  // Show minimum/maximum temperature
+  write_message("Minimum neutron data temperature: " +
+    std::to_string(data::temperature_min) + " K");
+  write_message("Maximum neutron data temperature: " +
+    std::to_string(data::temperature_max) + " K");
+
   // If the user wants multipole, make sure we found a multipole library.
   if (settings::temperature_multipole) {
     bool mp_found = false;

src/finalize.cpp

@@ -117,6 +117,8 @@ int openmc_finalize()
 
   data::energy_max = {INFTY, INFTY};
   data::energy_min = {0.0, 0.0};
+  data::temperature_min = 0.0;
+  data::temperature_max = INFTY;
   model::root_universe = -1;
   openmc::openmc_set_seed(DEFAULT_SEED);
 

src/nuclide.cpp

@@ -18,7 +18,7 @@
 #include "xtensor/xbuilder.hpp"
 #include "xtensor/xview.hpp"
 
-#include <algorithm> // for sort
+#include <algorithm> // for sort, min_element
 #include <string> // for to_string, stoi
 
 namespace openmc {
@@ -30,6 +30,8 @@ namespace openmc {
 namespace data {
 std::array<double, 2> energy_min {0.0, 0.0};
 std::array<double, 2> energy_max {INFTY, INFTY};
+double temperature_min {0.0};
+double temperature_max {INFTY};
 std::vector<std::unique_ptr<Nuclide>> nuclides;
 std::unordered_map<std::string, int> nuclide_map;
 } // namespace data
@@ -154,6 +156,12 @@ Nuclide::Nuclide(hid_t group, const std::vector<double>& temperature, int i_nucl
   // Sort temperatures to read
   std::sort(temps_to_read.begin(), temps_to_read.end());
 
+  double T_min_read = *std::min_element(temps_to_read.cbegin(), temps_to_read.cend());
+  double T_max_read = *std::max_element(temps_to_read.cbegin(), temps_to_read.cend());
+
+  data::temperature_min = std::max(data::temperature_min, T_min_read);
+  data::temperature_max = std::min(data::temperature_max, T_max_read);
+
   hid_t energy_group = open_group(group, "energy");
   for (const auto& T : temps_to_read) {
     std::string dset {std::to_string(T) + "K"};

tests/unit_tests/test_deplete_chain.py

@@ -360,3 +360,54 @@ def test_fission_yield_attribute(simple_chain):
     with pytest.raises(
             ValueError, match="fission yield.*not equal.*compositions"):
        cram.deplete(empty_chain, dummy_conc, None, 0.5)
+
+def test_validate(simple_chain):
+    """Test the validate method"""
+
+    # current chain is invalid
+    # fission yields do not sum to 2.0
+    with pytest.raises(ValueError, match="Nuclide C.*fission yields"):
+        simple_chain.validate(strict=True, tolerance=0.0)
+
+    with pytest.warns(UserWarning) as record:
+        assert not simple_chain.validate(strict=False, quiet=False, tolerance=0.0)
+        assert not simple_chain.validate(strict=False, quiet=True, tolerance=0.0)
+    assert len(record) == 1
+    assert "Nuclide C" in record[0].message.args[0]
+
+    # Fix fission yields but keep to restore later
+    old_yields = simple_chain["C"].yield_data
+    simple_chain["C"].yield_data = {0.0253: [("A", 1.4), ("B", 0.6)]}
+
+    assert simple_chain.validate(strict=True, tolerance=0.0)
+    with pytest.warns(None) as record:
+        assert simple_chain.validate(strict=False, quiet=False, tolerance=0.0)
+    assert len(record) == 0
+
+    # Mess up "earlier" nuclide's reactions
+    decay_mode = simple_chain["A"].decay_modes.pop()
+
+    with pytest.raises(ValueError, match="Nuclide A.*decay mode"):
+        simple_chain.validate(strict=True, tolerance=0.0)
+
+    # restore old fission yields
+    simple_chain["C"].yield_data = old_yields
+
+    with pytest.warns(UserWarning) as record:
+        assert not simple_chain.validate(strict=False, quiet=False, tolerance=0.0)
+    assert len(record) == 2
+    assert "Nuclide A" in record[0].message.args[0]
+    assert "Nuclide C" in record[1].message.args[0]
+
+    # restore decay modes
+    simple_chain["A"].decay_modes.append(decay_mode)
+
+
+def test_validate_inputs():
+    c = Chain()
+
+    with pytest.raises(TypeError, match="tolerance"):
+        c.validate(tolerance=None)
+
+    with pytest.raises(ValueError, match="tolerance"):
+        c.validate(tolerance=-1)

tests/unit_tests/test_deplete_nuclide.py

@@ -153,3 +153,91 @@ def test_fission_yield_distribution():
     assert numpy.array_equal(orig_yield_obj.yields * 2, mod_yields.yields)
     mod_yields += orig_yield_obj
     assert numpy.array_equal(orig_yield_obj.yields * 3, mod_yields.yields)
+
+def test_validate():
+
+    nuc = nuclide.Nuclide()
+    nuc.name = "Test"
+
+    # decay modes: type, target, branching_ratio
+
+    nuc.decay_modes = [
+        nuclide.DecayTuple("type 0", "0", 0.5),
+        nuclide.DecayTuple("type 1", "1", 0.5),
+    ]
+
+    # reactions: type, target, Q, branching_ratio
+    nuc.reactions = [
+        nuclide.ReactionTuple("0", "0", 1000, 0.3),
+        nuclide.ReactionTuple("0", "1", 1000, 0.3),
+        nuclide.ReactionTuple("1", "2", 1000, 1.0),
+        nuclide.ReactionTuple("0", "3", 1000, 0.4),
+    ]
+
+    # fission yields
+
+    nuc.yield_data = {
+        0.0253: [("0", 1.5), ("1", 0.5)],
+        1e6: [("0", 1.5), ("1", 0.5)],
+    }
+
+    # nuclide is good and should have no warnings raise
+    with pytest.warns(None) as record:
+        assert nuc.validate(strict=True, quiet=False, tolerance=0.0)
+    assert len(record) == 0
+
+    # invalidate decay modes
+    decay = nuc.decay_modes.pop()
+    with pytest.raises(ValueError, match="decay mode"):
+        nuc.validate(strict=True, quiet=False, tolerance=0.0)
+
+    with pytest.warns(UserWarning) as record:
+        assert not nuc.validate(strict=False, quiet=False, tolerance=0.0)
+        assert not nuc.validate(strict=False, quiet=True, tolerance=0.0)
+    assert len(record) == 1
+    assert "decay mode" in record[0].message.args[0]
+
+    # restore decay modes, invalidate reactions
+    nuc.decay_modes.append(decay)
+    reaction = nuc.reactions.pop()
+
+    with pytest.raises(ValueError, match="0 reaction"):
+        nuc.validate(strict=True, quiet=False, tolerance=0.0)
+
+    with pytest.warns(UserWarning) as record:
+        assert not nuc.validate(strict=False, quiet=False, tolerance=0.0)
+        assert not nuc.validate(strict=False, quiet=True, tolerance=0.0)
+    assert len(record) == 1
+    assert "0 reaction" in record[0].message.args[0]
+
+    # restore reactions, invalidate fission yields
+    nuc.reactions.append(reaction)
+    nuc.yield_data[1e6].pop()
+
+    with pytest.raises(ValueError, match=r"fission yields.*1\.0*e"):
+        nuc.validate(strict=True, quiet=False, tolerance=0.0)
+
+    with pytest.warns(UserWarning) as record:
+        assert not nuc.validate(strict=False, quiet=False, tolerance=0.0)
+        assert not nuc.validate(strict=False, quiet=True, tolerance=0.0)
+    assert len(record) == 1
+    assert "1.0" in record[0].message.args[0]
+
+    # invalidate everything, check that error is raised at decay modes
+
+    decay = nuc.decay_modes.pop()
+    reaction = nuc.reactions.pop()
+
+    with pytest.raises(ValueError, match="decay mode"):
+        nuc.validate(strict=True, quiet=False, tolerance=0.0)
+
+    # check for warnings
+    # should be one warning for decay modes, reactions, fission yields
+
+    with pytest.warns(UserWarning) as record:
+        assert not nuc.validate(strict=False, quiet=False, tolerance=0.0)
+        assert not nuc.validate(strict=False, quiet=True, tolerance=0.0)
+    assert len(record) == 3
+    assert "decay mode" in record[0].message.args[0]
+    assert "0 reaction" in record[1].message.args[0]
+    assert "1.0" in record[2].message.args[0]