diff --git a/openmc/config.py b/openmc/config.py
index d61fb2d31e6..874994f39ba 100644
--- a/openmc/config.py
+++ b/openmc/config.py
@@ -20,7 +20,6 @@
 from typing import Any, Dict, Iterator
 
 from openmc.data import DataLibrary
-from openmc.data.decay import _DECAY_ENERGY, _DECAY_PHOTON_ENERGY
 
 __all__ = ["config"]
 
@@ -76,9 +75,6 @@ def __delitem__(self, key: str):
             env_var = self._PATH_KEYS[key]
             if env_var in os.environ:
                 del os.environ[env_var]
-        if key == 'chain_file':
-            _DECAY_PHOTON_ENERGY.clear()
-            _DECAY_ENERGY.clear()
 
     def __setitem__(self, key: str, value: Any):
         """Set a configuration key and its corresponding value.
@@ -102,9 +98,6 @@ def __setitem__(self, key: str, value: Any):
             self._mapping[key] = stored_path
             os.environ[self._PATH_KEYS[key]] = str(stored_path)
 
-            if key == 'chain_file':
-                _DECAY_PHOTON_ENERGY.clear()
-                _DECAY_ENERGY.clear()
 
             if not stored_path.exists():
                 warnings.warn(f"Path '{stored_path}' does not exist.", UserWarning)
@@ -168,7 +161,10 @@ def patch(self, key: str, value: Any):
 
         """
         previous_value = self.get(key)
-        self[key] = value
+        if value is not None:
+            self[key] = value
+        else:
+            del self[key]
         try:
             yield
         finally:
diff --git a/openmc/data/data.py b/openmc/data/data.py
index 2142a5dc905..eb36ea7b59f 100644
--- a/openmc/data/data.py
+++ b/openmc/data/data.py
@@ -6,6 +6,8 @@
 from math import sqrt, log
 from warnings import warn
 
+from ..exceptions import DataError
+
 # Isotopic abundances from Meija J, Coplen T B, et al, "Isotopic compositions
 # of the elements 2013 (IUPAC Technical Report)", Pure. Appl. Chem. 88 (3),
 # pp. 293-306 (2013). The "representative isotopic abundance" values from
@@ -363,7 +365,7 @@ def atomic_weight(element):
         raise ValueError(f"No naturally-occurring isotopes for element '{element}'.")
 
 
-def half_life(isotope):
+def half_life(isotope, chain_file = None):
     """Return half-life of isotope in seconds or None if isotope is stable
 
     Half-life values are from the `ENDF/B-VIII.0 decay sublibrary
@@ -382,6 +384,15 @@ def half_life(isotope):
         Half-life of isotope in [s]
 
     """
+    from openmc.deplete.chain import _get_chain
+    
+    try:
+        chain = _get_chain(chain_file)
+        if isotope in chain and chain[isotope].half_life is not None:
+            return chain[isotope].half_life
+    except DataError:
+        pass
+    
     global _HALF_LIFE
     if not _HALF_LIFE:
         # Load ENDF/B-VIII.0 data from JSON file
@@ -391,7 +402,7 @@ def half_life(isotope):
     return _HALF_LIFE.get(isotope.lower())
 
 
-def decay_constant(isotope):
+def decay_constant(isotope, chain_file = None):
     """Return decay constant of isotope in [s^-1]
 
     Decay constants are based on half-life values from the
@@ -415,7 +426,7 @@ def decay_constant(isotope):
     openmc.data.half_life
 
     """
-    t = half_life(isotope)
+    t = half_life(isotope, chain_file = chain_file)
     return _LOG_TWO / t if t else 0.0
 
 
diff --git a/openmc/data/decay.py b/openmc/data/decay.py
index 1a11d3614fe..9c40e378482 100644
--- a/openmc/data/decay.py
+++ b/openmc/data/decay.py
@@ -569,10 +569,7 @@ def sources(self):
         return merged_sources
 
 
-_DECAY_PHOTON_ENERGY = {}
-
-
-def decay_photon_energy(nuclide: str) -> Univariate | None:
+def decay_photon_energy(nuclide: str, chain_file = None) -> Univariate | None:
     """Get photon energy distribution resulting from the decay of a nuclide
 
     This function relies on data stored in a depletion chain. Before calling it
@@ -585,6 +582,8 @@ def decay_photon_energy(nuclide: str) -> Univariate | None:
     ----------
     nuclide : str
         Name of nuclide, e.g., 'Co58'
+    chain_file : str or path-like
+        Chain file to get decay photon energy from.
 
     Returns
     -------
@@ -593,32 +592,20 @@ def decay_photon_energy(nuclide: str) -> Univariate | None:
         if no photon source exists. Note that the probabilities represent
         intensities, given as [Bq].
     """
-    if not _DECAY_PHOTON_ENERGY:
-        chain_file = openmc.config.get('chain_file')
-        if chain_file is None:
+    from openmc.deplete.chain import _get_chain
+    
+    chain = _get_chain(chain_file)
+    if chain is None:
             raise DataError(
                 "A depletion chain file must be specified with "
                 "openmc.config['chain_file'] in order to load decay data."
             )
-
-        from openmc.deplete import Chain
-        chain = Chain.from_xml(chain_file)
-        for nuc in chain.nuclides:
-            if 'photon' in nuc.sources:
-                _DECAY_PHOTON_ENERGY[nuc.name] = nuc.sources['photon']
-
-        # If the chain file contained no sources at all, warn the user
-        if not _DECAY_PHOTON_ENERGY:
-            warn(f"Chain file '{chain_file}' does not have any decay photon "
-                 "sources listed.")
-
-    return _DECAY_PHOTON_ENERGY.get(nuclide)
+    if nuclide in chain:
+        nuclide = chain[nuclide]
+        return nuclide.sources.get('photon')
 
 
-_DECAY_ENERGY = {}
-
-
-def decay_energy(nuclide: str):
+def decay_energy(nuclide: str, chain_file = None):
     """Get decay energy value resulting from the decay of a nuclide
 
     This function relies on data stored in a depletion chain. Before calling it
@@ -631,6 +618,8 @@ def decay_energy(nuclide: str):
     ----------
     nuclide : str
         Name of nuclide, e.g., 'H3'
+    chain_file : str or path-like
+        Chain file to get decay energy from.
 
     Returns
     -------
@@ -638,24 +627,18 @@ def decay_energy(nuclide: str):
         Decay energy of nuclide in [eV]. If the nuclide is stable, a value of
         0.0 is returned.
     """
-    if not _DECAY_ENERGY:
-        chain_file = openmc.config.get('chain_file')
-        if chain_file is None:
+    from openmc.deplete.chain import _get_chain
+    
+    chain = _get_chain(chain_file)
+    if chain is None:
             raise DataError(
                 "A depletion chain file must be specified with "
                 "openmc.config['chain_file'] in order to load decay data."
             )
+    if nuclide in chain:
+        nuclide = chain[nuclide]
+        return nuclide.decay_energy
 
-        from openmc.deplete import Chain
-        chain = Chain.from_xml(chain_file)
-        for nuc in chain.nuclides:
-            if nuc.decay_energy:
-                _DECAY_ENERGY[nuc.name] = nuc.decay_energy
-
-        # If the chain file contained no decay energy, warn the user
-        if not _DECAY_ENERGY:
-            warn(f"Chain file '{chain_file}' does not have any decay energy.")
-
-    return _DECAY_ENERGY.get(nuclide, 0.0)
+    return 0.0
 
 
diff --git a/openmc/deplete/abc.py b/openmc/deplete/abc.py
index e6d4c151273..7a5a69f91ba 100644
--- a/openmc/deplete/abc.py
+++ b/openmc/deplete/abc.py
@@ -19,7 +19,7 @@
 import numpy as np
 from uncertainties import ufloat
 
-from openmc.checkvalue import check_type, check_greater_than, PathLike
+from openmc.checkvalue import check_type, check_greater_than, check_value, PathLike
 from openmc.mpi import comm
 from openmc.utility_funcs import change_directory
 from openmc import Material
@@ -155,6 +155,7 @@ def __init__(self, chain_file=None, fission_q=None, prev_results=None):
             self.prev_res = None
         else:
             check_type("previous results", prev_results, Results)
+            check_value("previous results chain file", prev_results.chain, [self.chain])
             self.prev_res = prev_results
 
     @abstractmethod
diff --git a/openmc/deplete/chain.py b/openmc/deplete/chain.py
index f1a23317fb9..f0892cf7940 100644
--- a/openmc/deplete/chain.py
+++ b/openmc/deplete/chain.py
@@ -22,6 +22,7 @@
 from openmc.data import gnds_name, zam
 from openmc.exceptions import DataError
 from .nuclide import FissionYieldDistribution, Nuclide
+from ..mixin import EqualityMixin
 from .._xml import get_text
 import openmc.data
 
@@ -229,7 +230,7 @@ def replace_missing_fpy(actinide, fpy_data, decay_data):
     return 'U235'
 
 
-class Chain:
+class Chain(EqualityMixin):
     """Full representation of a depletion chain.
 
     A depletion chain can be created by using the :meth:`from_endf` method which
@@ -580,6 +581,50 @@ def export_to_xml(self, filename):
 
         tree = ET.ElementTree(root_elem)
         tree.write(str(filename), encoding='utf-8', pretty_print=True)
+        
+    @classmethod
+    def from_hdf5(cls, group, fission_q=None):
+        """Reads a depletion chain XML file.
+
+        Parameters
+        ----------
+        group : str
+            The hdf5 group to read depletion chain from.
+        fission_q : dict, optional
+            Dictionary of nuclides and their fission Q values [eV].
+            If not given, values will be pulled from ``filename``
+
+        """
+        cgroup = group["depletion_chain"]
+        if fission_q is not None:
+            check_type("fission_q", fission_q, Mapping)
+        else:
+            fission_q = {}
+        if "path" in cgroup.attrs:
+            path = Path(__file__).resolve().parent.joinpath(cgroup.attrs["path"])
+            return Chain.from_xml(path, fission_q)
+        else:
+            chain = cls()
+            nuc_group = cgroup["nuclides"]
+            for name, ngroup in nuc_group.items():
+                this_q = fission_q.get(name)
+                nuc = Nuclide.from_hdf5(nuc_group, name, this_q)
+                chain.add_nuclide(nuc)
+        
+    def to_hdf5(self, group):
+        cgroup = group.create_group("depletion_chain")
+        if hasattr(self, "_xml_path"):
+            path = Path(self._xml_path)
+            if openmc.config["resolve_paths"]:
+                path = path.resolve()
+            else:
+                path = path.relative_to(Path(__file__).resolve().parent, walk_up=True)
+            cgroup.attrs["path"] = str(path)
+        else:
+            nuc_group = cgroup.create_group("nuclides")
+            for nuclide in self.nuclides:
+                nuclide.to_hdf5(nuc_group)
+        
 
     def get_default_fission_yields(self):
         """Return fission yields at lowest incident neutron energy
diff --git a/openmc/deplete/nuclide.py b/openmc/deplete/nuclide.py
index 95881483474..d2f0c4691f0 100644
--- a/openmc/deplete/nuclide.py
+++ b/openmc/deplete/nuclide.py
@@ -343,6 +343,125 @@ def to_xml_element(self):
                 self.yield_data.to_xml_element(fpy_elem)
 
         return elem
+        
+    @classmethod
+    def from_hdf5(cls, group, name, fission_q=None):
+        """Read nuclide from a hdf5 group.
+
+        Parameters
+        ----------
+        group : h5py.Group
+            hdf5 group to read nuclide data from
+        fission_q : None or float
+            User-supplied fission Q value [eV].
+            Will be read from the group if not given
+
+        Returns
+        -------
+        nuc : openmc.deplete.Nuclide
+            Instance of a nuclide
+
+        """
+        nuc = cls()
+        nuc.name = name
+
+        # Check for half-life
+        if "decay" in group[name]:
+            nuc.half_life = float(group[name]["decay"].attrs["half_life"])
+            nuc.decay_energy = float(group[name]["decay"].attrs.get("decay_energy", 0.0))
+            
+            # Check for decay paths
+            for dgroup in group[name]["decay"].values():
+                d_type = dgroup.attrs["type"]
+                target = dgroup.attrs.get("target")
+                if target is not None and target.lower() == "nothing":
+                     target = None
+                branching_ratio = float(dgroup.attrs.get("branching_ratio", 1.0))
+                nuc.decay_modes.append(DecayTuple(d_type, target, branching_ratio))
+
+        # Check for sources
+        if "sources" in group[name]:
+            for particle, sgroup in group[name]["sources"].items():
+                distribution = Univariate.from_hdf5(sgroup)
+                nuc.sources[particle] = distribution
+
+        # Check for reaction paths
+        if "reactions" in group[name]:
+            for rgroup in group[name]["reactions"].values():
+                r_type = rgroup.attrs["type"]
+                Q = rgroup.attrs.get("Q", 0.0)
+                branching_ratio = rgroup.attrs.get("branching_ratio", 1.0)
+
+                # If the type is not fission, get target and Q value, otherwise
+                # just set null values
+                if r_type != 'fission':
+                    target = rgroup.attrs.get("target")
+                    if target is not None and target.lower() == "nothing":
+                        target = None
+                else:
+                    target = None
+                    if fission_q is not None:
+                        Q = fission_q
+
+                # Append reaction
+                nuc.reactions.append(ReactionTuple(
+                    r_type, target, Q, branching_ratio))
+
+        if "neutron_fission_yields" in group[name]:
+            parent = group[name]["neutron_fission_yields"].attrs.get("parent")
+            if parent is not None:
+                if "neutron_fission_yields" not in group[parent]:
+                    raise ValueError(
+                        "Fission product yields for {0} borrow from {1}, but {1} is"
+                        " not present in the chain file or has no yields.".format(
+                            name, parent
+                        ))
+                nuc.yield_data = FissionYieldDistribution.from_hdf5(group[parent]["neutron_fission_yields"])
+                nuc._fpy = parent
+            else:
+                nuc.yield_data = FissionYieldDistribution.from_hdf5(group[name]["neutron_fission_yields"])
+        return nuc
+        
+    def to_hdf5(self, group):
+        """Write nuclide to hdf5."""
+        group = group.create_group(self.name)
+        
+        if self.half_life is not None:
+            dec_group = group.create_group("decay")
+            dec_group.attrs['half_life'] = self.half_life
+            dec_group.attrs['decay_energy'] = self.decay_energy
+            
+            for i, (mode_type, daughter, br) in enumerate(self.decay_modes):
+                mgroup = dec_group.create_group(f"mode_{i:01d}")
+                mgroup.attrs["type"] = mode_type
+                if daughter:
+                    mgroup.attrs["target"] = daughter
+                mgroup.attrs["branching_ratio"] = br
+
+        # Write decay sources
+        if self.sources:
+            sources_group = group.create_group("sources")
+            for particle, source in self.sources.items():
+                pgroup = sources_group.create_group(particle)
+                source.to_hdf5(pgroup)
+  
+        reac_group = group.create_group("reactions")
+        for i, (rx, daughter, Q, br) in enumerate(self.reactions):
+            rgroup = reac_group.create_group(f"reaction_{i:03d}")
+            rgroup.attrs["type"] = rx
+            rgroup.attrs["Q"] = Q
+            if daughter is not None:
+                rgroup.attrs["target"] = daughter
+            if br != 1.0:
+                rgroup.attrs["branching_ratio"] = br
+
+        if self.yield_data:
+            nfy_group = group.create_group("neutron_fission_yields")
+            if hasattr(self, '_fpy'):
+                # Check for link to other nuclide data
+                nfy_group.attrs["parent"] = self._fpy
+            else:
+                self.yield_data.to_hdf5(nfy_group)
 
     def validate(self, strict=True, quiet=False, tolerance=1e-4):
         """Search for possible inconsistencies
@@ -554,6 +673,25 @@ def to_xml_element(self, root):
             product_elem.text = " ".join(map(str, yield_obj.products))
             data_elem = ET.SubElement(yield_element, "data")
             data_elem.text = " ".join(map(str, yield_obj.yields))
+            
+    @classmethod
+    def from_hdf5(cls, group):
+        all_yields = {}
+        for egroup in group.values():
+            energy = egroup.attrs["energy"]
+            products = egroup["products"][()]
+            yields = egroup["yields"][()]
+            # Get a map of products to their corresponding yield
+            all_yields[energy] = dict(zip(products, yields))
+
+        return cls(all_yields)
+
+    def to_hdf5(self, group):
+        for energy, yield_obj in self.items():
+            egroup = group.create_group(f"{energy}eV")
+            egroup.attrs["energy"] = energy
+            egroup.create_dataset("products", data = yield_obj.products)
+            egroup.create_dataset("yields", data = yield_obj.yields)
 
     def restrict_products(self, possible_products):
         """Return a new distribution with select products
diff --git a/openmc/deplete/results.py b/openmc/deplete/results.py
index 7427abd7353..294ed583511 100644
--- a/openmc/deplete/results.py
+++ b/openmc/deplete/results.py
@@ -2,11 +2,13 @@
 import bisect
 import math
 from collections.abc import Iterable
+from pathlib import Path
 from warnings import warn
 
 import h5py
 import numpy as np
 
+from .chain import Chain
 from .stepresult import StepResult, VERSION_RESULTS
 import openmc.checkvalue as cv
 from openmc.data import atomic_mass, AVOGADRO
@@ -69,6 +71,8 @@ def __init__(self, filename='depletion_results.h5'):
             with h5py.File(str(filename), "r") as fh:
                 cv.check_filetype_version(fh, 'depletion results', VERSION_RESULTS[0])
 
+                self.chain = Chain.from_hdf5(fh)
+                
                 # Get number of results stored
                 n = fh["number"][...].shape[0]
 
@@ -149,7 +153,7 @@ def get_activity(
         # Evaluate activity for each depletion time
         for i, result in enumerate(self):
             times[i] = result.time[0]
-            activities[i] = result.get_material(mat_id).get_activity(units, by_nuclide, volume)
+            activities[i] = result.get_material(mat_id).get_activity(units, by_nuclide, volume, chain_file = self.chain)
 
         return times, activities
 
@@ -268,7 +272,7 @@ def get_decay_heat(
         for i, result in enumerate(self):
             times[i] = result.time[0]
             decay_heat[i] = result.get_material(mat_id).get_decay_heat(
-                units, by_nuclide, volume)
+                units, by_nuclide, volume, chain_file = self.chain)
 
         return times, decay_heat
 
diff --git a/openmc/deplete/stepresult.py b/openmc/deplete/stepresult.py
index 1a26cbe3466..1b5fccd3f63 100644
--- a/openmc/deplete/stepresult.py
+++ b/openmc/deplete/stepresult.py
@@ -12,6 +12,7 @@
 import numpy as np
 
 import openmc
+import openmc.checkvalue as cv
 from openmc.mpi import comm, MPI
 from openmc.checkvalue import PathLike
 from .reaction_rates import ReactionRates
@@ -252,7 +253,7 @@ def export_to_hdf5(self, filename, step):
 
         """
         # Write new file if first time step, else add to existing file
-        kwargs = {'mode': "w" if step == 0 else "a"}
+        kwargs = {'mode': "a"}
 
         if h5py.get_config().mpi and comm.size > 1:
             # Write results in parallel
@@ -567,6 +568,25 @@ def save(op, x, op_results, t, source_rate, step_ind, proc_time=None,
 
         if not Path(path).is_file():
             Path(path).parent.mkdir(parents=True, exist_ok=True)
+        
+        filename = str(path)
+        
+        if step_ind == 0:    
+            # Write new file if first time step, else add to existing file
+            kwargs = {'mode': "w"}
+
+            if h5py.get_config().mpi and comm.size > 1:
+                # Write results in parallel
+                kwargs['driver'] = 'mpio'
+                kwargs['comm'] = comm
+                with h5py.File(filename, **kwargs) as handle:
+                    op.chain.to_hdf5(handle)
+            else:
+                # Only root process writes depletion chain
+                if comm.rank == 0:
+                    with h5py.File(filename, **kwargs) as handle:
+                        op.chain.to_hdf5(handle)
+                                    
         results.export_to_hdf5(path, step_ind)
 
     def transfer_volumes(self, model):
diff --git a/openmc/material.py b/openmc/material.py
index c7b954b6666..812db0886eb 100644
--- a/openmc/material.py
+++ b/openmc/material.py
@@ -293,7 +293,8 @@ def get_decay_photon_energy(
             self,
             clip_tolerance: float = 1e-6,
             units: str = 'Bq',
-            volume: float | None = None
+            volume: float | None = None, 
+            chain_file: str | Path | None = None,
         ) -> Univariate | None:
         r"""Return energy distribution of decay photons from unstable nuclides.
 
@@ -309,6 +310,8 @@ def get_decay_photon_energy(
         volume : float, optional
             Volume of the material. If not passed, defaults to using the
             :attr:`Material.volume` attribute.
+        chain_file : str or path-like, optional.
+            Location of chain file to get decay constants from.                
 
         Returns
         -------
@@ -332,7 +335,7 @@ def get_decay_photon_energy(
         dists = []
         probs = []
         for nuc, atoms_per_bcm in self.get_nuclide_atom_densities().items():
-            source_per_atom = openmc.data.decay_photon_energy(nuc)
+            source_per_atom = openmc.data.decay_photon_energy(nuc, chain_file=chain_file)
             if source_per_atom is not None and atoms_per_bcm > 0.0:
                 dists.append(source_per_atom)
                 probs.append(1e24 * atoms_per_bcm * multiplier)
@@ -1139,7 +1142,7 @@ def get_element_atom_densities(self, element: str | None = None) -> dict[str, fl
 
 
     def get_activity(self, units: str = 'Bq/cm3', by_nuclide: bool = False,
-                     volume: float | None = None) -> dict[str, float] | float:
+                     volume: float | None = None, chain_file: str | Path | None = None) -> dict[str, float] | float:
         """Returns the activity of the material or of each nuclide within.
 
         .. versionadded:: 0.13.1
@@ -1156,6 +1159,8 @@ def get_activity(self, units: str = 'Bq/cm3', by_nuclide: bool = False,
         volume : float, optional
             Volume of the material. If not passed, defaults to using the
             :attr:`Material.volume` attribute.
+        chain_file : str or path-like, optional.
+            Location of chain file to get decay constants from.    
 
             .. versionadded:: 0.13.3
 
@@ -1188,13 +1193,13 @@ def get_activity(self, units: str = 'Bq/cm3', by_nuclide: bool = False,
 
         activity = {}
         for nuclide, atoms_per_bcm in self.get_nuclide_atom_densities().items():
-            inv_seconds = openmc.data.decay_constant(nuclide)
+            inv_seconds = openmc.data.decay_constant(nuclide, chain_file = chain_file)
             activity[nuclide] = inv_seconds * 1e24 * atoms_per_bcm * multiplier
 
         return activity if by_nuclide else sum(activity.values())
 
     def get_decay_heat(self, units: str = 'W', by_nuclide: bool = False,
-                       volume: float | None = None) -> dict[str, float] | float:
+                       volume: float | None = None, chain_file: str | Path | None = None) -> dict[str, float] | float:
         """Returns the decay heat of the material or for each nuclide in the
         material in units of [W], [W/g], [W/kg] or [W/cm3].
 
@@ -1212,6 +1217,8 @@ def get_decay_heat(self, units: str = 'W', by_nuclide: bool = False,
         volume : float, optional
             Volume of the material. If not passed, defaults to using the
             :attr:`Material.volume` attribute.
+        chain_file : str or path-like, optional.
+            Location of chain file to get decay constants from.    
 
             .. versionadded:: 0.13.3
 
@@ -1237,8 +1244,8 @@ def get_decay_heat(self, units: str = 'W', by_nuclide: bool = False,
 
         decayheat = {}
         for nuclide, atoms_per_bcm in self.get_nuclide_atom_densities().items():
-            decay_erg = openmc.data.decay_energy(nuclide)
-            inv_seconds = openmc.data.decay_constant(nuclide)
+            decay_erg = openmc.data.decay_energy(nuclide, chain_file=chain_file)
+            inv_seconds = openmc.data.decay_constant(nuclide, chain_file=chain_file)
             decay_erg *= openmc.data.JOULE_PER_EV
             decayheat[nuclide] = inv_seconds * decay_erg * 1e24 * atoms_per_bcm * multiplier
 
diff --git a/openmc/stats/univariate.py b/openmc/stats/univariate.py
index 28d5e87ef9e..47e88835fe8 100644
--- a/openmc/stats/univariate.py
+++ b/openmc/stats/univariate.py
@@ -31,6 +31,10 @@ class Univariate(EqualityMixin, ABC):
     specific probability distribution.
 
     """
+    @abstractmethod
+    def to_hdf5(self, group):
+        return
+    
     @abstractmethod
     def to_xml_element(self, element_name):
         return ''
@@ -64,6 +68,30 @@ def from_xml_element(cls, elem):
             return Legendre.from_xml_element(elem)
         elif distribution == 'mixture':
             return Mixture.from_xml_element(elem)
+            
+    @classmethod
+    @abstractmethod
+    def from_hdf5(cls, group):
+        distribution = group.attrs["type"]
+        if distribution == 'discrete':
+            return Discrete.from_hdf5(group)
+        elif distribution == 'uniform':
+            return Uniform.from_hdf5(group)
+        elif distribution == 'powerlaw':
+            return PowerLaw.from_hdf5(group)
+        elif distribution == 'maxwell':
+            return Maxwell.from_hdf5(group)
+        elif distribution == 'watt':
+            return Watt.from_hdf5(group)
+        elif distribution == 'normal':
+            return Normal.from_hdf5(group)
+        elif distribution == 'tabular':
+            return Tabular.from_hdf5(group)
+        elif distribution == 'legendre':
+            return Legendre.from_hdf5(group)
+        elif distribution == 'mixture':
+            return Mixture.from_hdf5(group)
+            
 
     @abstractmethod
     def sample(n_samples: int = 1, seed: int | None = None):
@@ -244,6 +272,17 @@ def from_xml_element(cls, elem: ET.Element):
         p = params[len(params)//2:]
         return cls(x, p)
 
+    def to_hdf5(self, group):
+        group.attrs["type"] = "discrete"
+        group.create_dataset("parameters", data=np.r_[self.x,self.p])
+        
+    @classmethod
+    def from_hdf5(cls, group):
+        params = group["parameters"][()]
+        x = params[:len(params)//2]
+        p = params[len(params)//2:]
+        return cls(x, p)        
+
     @classmethod
     def merge(
         cls,
@@ -450,6 +489,14 @@ def from_xml_element(cls, elem: ET.Element):
         params = get_elem_list(elem, "parameters", float)
         return cls(*params)
 
+    def to_hdf5(self, group):
+        group.attrs["type"] = "uniform"
+        group.create_dataset("parameters", data=np.r_[self.a,self.b])
+        
+    @classmethod
+    def from_hdf5(cls, group):
+        params = group["parameters"][()]
+        return cls(*params)
 
 class PowerLaw(Univariate):
     """Distribution with power law probability over a finite interval [a,b]
@@ -558,7 +605,15 @@ def from_xml_element(cls, elem: ET.Element):
         """
         params = get_elem_list(elem, "parameters", float)
         return cls(*params)
-
+        
+    def to_hdf5(self, group):
+        group.attrs["type"] = "powerlaw"
+        group.create_dataset("parameters", data=np.r_[self.a,self.b,self.n])
+        
+    @classmethod
+    def from_hdf5(cls, group):
+        params = group["parameters"][()]
+        return cls(*params)
 
 class Maxwell(Univariate):
     r"""Maxwellian distribution in energy.
@@ -644,6 +699,14 @@ def from_xml_element(cls, elem: ET.Element):
         theta = float(get_text(elem, 'parameters'))
         return cls(theta)
 
+    def to_hdf5(self, group):
+        group.attrs["type"] = "maxwell"
+        group.attrs["theta"] = self.theta
+
+    @classmethod
+    def from_hdf5(cls, group):
+        theta = group.attrs["theta"]
+        return cls(theta)
 
 class Watt(Univariate):
     r"""Watt fission energy spectrum.
@@ -739,6 +802,14 @@ def from_xml_element(cls, elem: ET.Element):
         params = get_elem_list(elem, "parameters", float)
         return cls(*params)
 
+    def to_hdf5(self, group):
+        group.attrs["type"] = "watt"
+        group.create_dataset("parameters", data=np.r_[self.a,self.b])
+        
+    @classmethod
+    def from_hdf5(cls, group):
+        params = group["parameters"][()]
+        return cls(*params)
 
 class Normal(Univariate):
     r"""Normally distributed sampling.
@@ -829,6 +900,14 @@ def from_xml_element(cls, elem: ET.Element):
         params = get_elem_list(elem, "parameters", float)
         return cls(*params)
 
+    def to_hdf5(self, group):
+        group.attrs["type"] = "normal"
+        group.create_dataset("parameters", data=np.r_[self.mean_value,self.std_dev])
+        
+    @classmethod
+    def from_hdf5(cls, group):
+        params = group["parameters"][()]
+        return cls(*params)
 
 def muir(e0: float, m_rat: float, kt: float):
     """Generate a Muir energy spectrum
@@ -1119,7 +1198,21 @@ def from_xml_element(cls, elem: ET.Element):
         x = params[:m]
         p = params[m:]
         return cls(x, p, interpolation)
-
+        
+    def to_hdf5(self, group):
+        group.attrs["type"] = "tabular"
+        group.attrs["interpolation"] = self.interpolation
+        group.create_dataset("parameters", data=np.r_[self.x,self.p])
+        
+    @classmethod
+    def from_hdf5(cls, group):
+        interpolation = group.attrs["interpolation"]
+        params = group["parameters"][()]
+        m = (len(params) + 1)//2  # +1 for when len(params) is odd
+        x = params[:m]
+        p = params[m:]
+        return cls(x, p, interpolation)
+        
     def integral(self):
         """Return integral of distribution
 
@@ -1190,6 +1283,13 @@ def to_xml_element(self, element_name):
     @classmethod
     def from_xml_element(cls, elem):
         raise NotImplementedError
+        
+    def to_hdf5(self, group):
+        raise NotImplementedError
+
+    @classmethod
+    def from_hdf5(cls, group):
+        raise NotImplementedError        
 
 
 class Mixture(Univariate):
@@ -1323,6 +1423,23 @@ def from_xml_element(cls, elem: ET.Element):
 
         return cls(probability, distribution)
 
+    def to_hdf5(self, group):
+        group.attrs["type"] = "mixture"
+        for i, (p, d) in enumerate(zip(self.probability, self.distribution)):
+          dgroup = group.create_group(f"dist_{i:d}")
+          dgroup.attrs["probability"] = p
+          d.to_hdf5(dgroup)
+
+    @classmethod
+    def from_hdf5(cls, group):
+        probability = []
+        distribution = []
+        for dgroup in group.values():
+            probability.append(dgroup.attrs["probability"])
+            distribution.append(Univariate.from_hdf5(dgroup))
+
+        return cls(probability, distribution)
+        
     def integral(self):
         """Return integral of the distribution
 
diff --git a/tests/dummy_operator.py b/tests/dummy_operator.py
index 1bb00129d04..869a5f0c8dc 100644
--- a/tests/dummy_operator.py
+++ b/tests/dummy_operator.py
@@ -115,6 +115,9 @@ def form_matrix(self, rates, _fission_yields=None):
         a22 = np.sin(y_1)
 
         return sp.csr_matrix(np.array([[a11, a12], [a21, a22]]))
+        
+    def to_hdf5(self, group):
+        group.create_group("depletion_chain").create_group("nuclides")
 
 
 class DummyOperator(TransportOperator):
diff --git a/tests/regression_tests/deplete_no_transport/test_reference_coupled_days.h5 b/tests/regression_tests/deplete_no_transport/test_reference_coupled_days.h5
index 5fdc656d970..4cdfff0a989 100644
Binary files a/tests/regression_tests/deplete_no_transport/test_reference_coupled_days.h5 and b/tests/regression_tests/deplete_no_transport/test_reference_coupled_days.h5 differ
diff --git a/tests/regression_tests/deplete_no_transport/test_reference_coupled_hours.h5 b/tests/regression_tests/deplete_no_transport/test_reference_coupled_hours.h5
index 65bfc19a91c..adbcbc69aed 100644
Binary files a/tests/regression_tests/deplete_no_transport/test_reference_coupled_hours.h5 and b/tests/regression_tests/deplete_no_transport/test_reference_coupled_hours.h5 differ
diff --git a/tests/regression_tests/deplete_no_transport/test_reference_coupled_minutes.h5 b/tests/regression_tests/deplete_no_transport/test_reference_coupled_minutes.h5
index 294cb589f7b..b997e46f938 100644
Binary files a/tests/regression_tests/deplete_no_transport/test_reference_coupled_minutes.h5 and b/tests/regression_tests/deplete_no_transport/test_reference_coupled_minutes.h5 differ
diff --git a/tests/regression_tests/deplete_no_transport/test_reference_coupled_months.h5 b/tests/regression_tests/deplete_no_transport/test_reference_coupled_months.h5
index ed62e461049..6d9e532e9ad 100644
Binary files a/tests/regression_tests/deplete_no_transport/test_reference_coupled_months.h5 and b/tests/regression_tests/deplete_no_transport/test_reference_coupled_months.h5 differ
diff --git a/tests/regression_tests/deplete_no_transport/test_reference_fission_q.h5 b/tests/regression_tests/deplete_no_transport/test_reference_fission_q.h5
index 9d32d89fe23..a106d61b6c4 100644
Binary files a/tests/regression_tests/deplete_no_transport/test_reference_fission_q.h5 and b/tests/regression_tests/deplete_no_transport/test_reference_fission_q.h5 differ
diff --git a/tests/regression_tests/deplete_no_transport/test_reference_source_rate.h5 b/tests/regression_tests/deplete_no_transport/test_reference_source_rate.h5
index 3f3b4aa2ac5..fd4d3fd86e7 100644
Binary files a/tests/regression_tests/deplete_no_transport/test_reference_source_rate.h5 and b/tests/regression_tests/deplete_no_transport/test_reference_source_rate.h5 differ
diff --git a/tests/regression_tests/deplete_with_transfer_rates/ref_depletion_with_ext_source.h5 b/tests/regression_tests/deplete_with_transfer_rates/ref_depletion_with_ext_source.h5
index aa09e1bcf4e..b9b80984acb 100644
Binary files a/tests/regression_tests/deplete_with_transfer_rates/ref_depletion_with_ext_source.h5 and b/tests/regression_tests/deplete_with_transfer_rates/ref_depletion_with_ext_source.h5 differ
diff --git a/tests/regression_tests/deplete_with_transfer_rates/ref_depletion_with_feed.h5 b/tests/regression_tests/deplete_with_transfer_rates/ref_depletion_with_feed.h5
index 284d5cbe4ed..ca5e34377db 100644
Binary files a/tests/regression_tests/deplete_with_transfer_rates/ref_depletion_with_feed.h5 and b/tests/regression_tests/deplete_with_transfer_rates/ref_depletion_with_feed.h5 differ
diff --git a/tests/regression_tests/deplete_with_transfer_rates/ref_depletion_with_removal.h5 b/tests/regression_tests/deplete_with_transfer_rates/ref_depletion_with_removal.h5
index 271af24103c..42870552e5f 100644
Binary files a/tests/regression_tests/deplete_with_transfer_rates/ref_depletion_with_removal.h5 and b/tests/regression_tests/deplete_with_transfer_rates/ref_depletion_with_removal.h5 differ
diff --git a/tests/regression_tests/deplete_with_transfer_rates/ref_depletion_with_transfer.h5 b/tests/regression_tests/deplete_with_transfer_rates/ref_depletion_with_transfer.h5
index 25365f6f3a4..9ae9400edda 100644
Binary files a/tests/regression_tests/deplete_with_transfer_rates/ref_depletion_with_transfer.h5 and b/tests/regression_tests/deplete_with_transfer_rates/ref_depletion_with_transfer.h5 differ
diff --git a/tests/regression_tests/deplete_with_transfer_rates/ref_no_depletion_only_feed.h5 b/tests/regression_tests/deplete_with_transfer_rates/ref_no_depletion_only_feed.h5
index d080b447093..f8e3e6c0004 100644
Binary files a/tests/regression_tests/deplete_with_transfer_rates/ref_no_depletion_only_feed.h5 and b/tests/regression_tests/deplete_with_transfer_rates/ref_no_depletion_only_feed.h5 differ
diff --git a/tests/regression_tests/deplete_with_transfer_rates/ref_no_depletion_only_removal.h5 b/tests/regression_tests/deplete_with_transfer_rates/ref_no_depletion_only_removal.h5
index 36f89e0090b..c5d1e27a746 100644
Binary files a/tests/regression_tests/deplete_with_transfer_rates/ref_no_depletion_only_removal.h5 and b/tests/regression_tests/deplete_with_transfer_rates/ref_no_depletion_only_removal.h5 differ
diff --git a/tests/regression_tests/deplete_with_transfer_rates/ref_no_depletion_with_ext_source.h5 b/tests/regression_tests/deplete_with_transfer_rates/ref_no_depletion_with_ext_source.h5
index f3b1b171ebc..7b9c0c11db5 100644
Binary files a/tests/regression_tests/deplete_with_transfer_rates/ref_no_depletion_with_ext_source.h5 and b/tests/regression_tests/deplete_with_transfer_rates/ref_no_depletion_with_ext_source.h5 differ
diff --git a/tests/regression_tests/deplete_with_transfer_rates/ref_no_depletion_with_transfer.h5 b/tests/regression_tests/deplete_with_transfer_rates/ref_no_depletion_with_transfer.h5
index b0ba997407f..e5ee6490aa0 100644
Binary files a/tests/regression_tests/deplete_with_transfer_rates/ref_no_depletion_with_transfer.h5 and b/tests/regression_tests/deplete_with_transfer_rates/ref_no_depletion_with_transfer.h5 differ
diff --git a/tests/regression_tests/deplete_with_transport/last_step_reference_materials.xml b/tests/regression_tests/deplete_with_transport/last_step_reference_materials.xml
index 242e2e7db5f..6370466e482 100644
--- a/tests/regression_tests/deplete_with_transport/last_step_reference_materials.xml
+++ b/tests/regression_tests/deplete_with_transport/last_step_reference_materials.xml
@@ -4,469 +4,469 @@
     <density units="sum"/>
     <nuclide name="O16" ao="0.046295399999999994"/>
     <nuclide name="O17" ao="0.00011276839999999999"/>
-    <nuclide name="Cs135" ao="4.4180489845847837e-07"/>
-    <nuclide name="Gd156" ao="7.2549793284842195e-09"/>
-    <nuclide name="Gd157" ao="4.6150717465438587e-10"/>
-    <nuclide name="I135" ao="8.610759149890541e-09"/>
+    <nuclide name="Cs135" ao="4.418048984584777e-07"/>
+    <nuclide name="Gd156" ao="7.25497932848423e-09"/>
+    <nuclide name="Gd157" ao="4.6150717465438633e-10"/>
+    <nuclide name="I135" ao="8.610759149890548e-09"/>
     <nuclide name="U234" ao="1.00447595096247e-05"/>
-    <nuclide name="U235" ao="0.001021319968105753"/>
-    <nuclide name="U238" ao="0.022134492490415457"/>
-    <nuclide name="Xe135" ao="4.898883540853392e-09"/>
-    <nuclide name="Xe136" ao="1.5016036288896978e-06"/>
+    <nuclide name="U235" ao="0.0010213199681057535"/>
+    <nuclide name="U238" ao="0.022134492490415478"/>
+    <nuclide name="Xe135" ao="4.898883540853396e-09"/>
+    <nuclide name="Xe136" ao="1.5016036288896986e-06"/>
   </material>
   <material id="2" depletable="true" volume="0.06674732823364922" temperature="293.6">
     <density units="sum"/>
     <nuclide name="O16" ao="0.046295399999999994"/>
     <nuclide name="O17" ao="0.00011276839999999999"/>
-    <nuclide name="Cs135" ao="4.7109992046231964e-07"/>
-    <nuclide name="Gd156" ao="7.042063874024541e-09"/>
-    <nuclide name="Gd157" ao="6.027071887061818e-10"/>
-    <nuclide name="I135" ao="7.95412956238769e-09"/>
+    <nuclide name="Cs135" ao="4.710999204623192e-07"/>
+    <nuclide name="Gd156" ao="7.042063874024543e-09"/>
+    <nuclide name="Gd157" ao="6.027071887061815e-10"/>
+    <nuclide name="I135" ao="7.954129562387692e-09"/>
     <nuclide name="U234" ao="1.0044351820098593e-05"/>
     <nuclide name="U235" ao="0.00102408632740032"/>
-    <nuclide name="U238" ao="0.02213423274784442"/>
-    <nuclide name="Xe135" ao="4.973037106302515e-09"/>
-    <nuclide name="Xe136" ao="1.3283930174680673e-06"/>
+    <nuclide name="U238" ao="0.022134232747844398"/>
+    <nuclide name="Xe135" ao="4.973037106302517e-09"/>
+    <nuclide name="Xe136" ao="1.3283930174680677e-06"/>
   </material>
   <material id="3" depletable="true" volume="0.06674732823364922" temperature="293.6">
     <density units="sum"/>
     <nuclide name="O16" ao="0.046295399999999994"/>
     <nuclide name="O17" ao="0.00011276839999999999"/>
-    <nuclide name="Cs135" ao="4.5196882278137964e-07"/>
-    <nuclide name="Gd156" ao="7.390520641508283e-09"/>
-    <nuclide name="Gd157" ao="6.1139624340991e-10"/>
+    <nuclide name="Cs135" ao="4.5196882278137975e-07"/>
+    <nuclide name="Gd156" ao="7.390520641508288e-09"/>
+    <nuclide name="Gd157" ao="6.113962434099102e-10"/>
     <nuclide name="I135" ao="7.339426249127244e-09"/>
-    <nuclide name="U234" ao="1.0044458911815349e-05"/>
+    <nuclide name="U234" ao="1.0044458911815357e-05"/>
     <nuclide name="U235" ao="0.0010213846058415266"/>
-    <nuclide name="U238" ao="0.02213428321817386"/>
+    <nuclide name="U238" ao="0.022134283218173886"/>
     <nuclide name="Xe135" ao="5.052047240880656e-09"/>
-    <nuclide name="Xe136" ao="1.492502282115296e-06"/>
+    <nuclide name="Xe136" ao="1.4925022821152953e-06"/>
   </material>
   <material id="4" depletable="true" volume="0.06674732823364922" temperature="293.6">
     <density units="sum"/>
     <nuclide name="O16" ao="0.046295399999999994"/>
     <nuclide name="O17" ao="0.00011276839999999999"/>
-    <nuclide name="Cs135" ao="4.610385562797368e-07"/>
-    <nuclide name="Gd156" ao="7.2542350999039044e-09"/>
+    <nuclide name="Cs135" ao="4.610385562797373e-07"/>
+    <nuclide name="Gd156" ao="7.254235099903903e-09"/>
     <nuclide name="Gd157" ao="4.694384504892065e-10"/>
-    <nuclide name="I135" ao="8.99963252548058e-09"/>
-    <nuclide name="U234" ao="1.0044557857503748e-05"/>
-    <nuclide name="U235" ao="0.0010213889405514816"/>
-    <nuclide name="U238" ao="0.022134477440110358"/>
-    <nuclide name="Xe135" ao="5.198618342135029e-09"/>
-    <nuclide name="Xe136" ao="1.4782292628750817e-06"/>
+    <nuclide name="I135" ao="8.999632525480592e-09"/>
+    <nuclide name="U234" ao="1.004455785750376e-05"/>
+    <nuclide name="U235" ao="0.001021388940551483"/>
+    <nuclide name="U238" ao="0.02213447744011035"/>
+    <nuclide name="Xe135" ao="5.1986183421350376e-09"/>
+    <nuclide name="Xe136" ao="1.4782292628750815e-06"/>
   </material>
   <material id="5" depletable="true" volume="0.06674732823364922" temperature="293.6">
     <density units="sum"/>
     <nuclide name="O16" ao="0.0464035"/>
     <nuclide name="Cs135" ao="4.6068906575995227e-07"/>
-    <nuclide name="Gd156" ao="4.45301183633431e-09"/>
-    <nuclide name="Gd157" ao="6.452882105032804e-05"/>
-    <nuclide name="I135" ao="5.350905347436304e-09"/>
+    <nuclide name="Gd156" ao="4.4530118363343095e-09"/>
+    <nuclide name="Gd157" ao="6.452882105032818e-05"/>
+    <nuclide name="I135" ao="5.3509053474363066e-09"/>
     <nuclide name="U235" ao="0.0010186933910628446"/>
-    <nuclide name="U238" ao="0.02169176973824294"/>
-    <nuclide name="Xe135" ao="6.032753962430652e-09"/>
-    <nuclide name="Xe136" ao="4.88334256170519e-07"/>
+    <nuclide name="U238" ao="0.021691769738242935"/>
+    <nuclide name="Xe135" ao="6.032753962430655e-09"/>
+    <nuclide name="Xe136" ao="4.883342561705191e-07"/>
   </material>
   <material id="6" depletable="true" volume="0.06674732823364922" temperature="293.6">
     <density units="sum"/>
     <nuclide name="O16" ao="0.046295399999999994"/>
     <nuclide name="O17" ao="0.00011276839999999999"/>
-    <nuclide name="Cs135" ao="4.5448917916965475e-07"/>
-    <nuclide name="Gd156" ao="7.987183377412963e-09"/>
+    <nuclide name="Cs135" ao="4.5448917916965506e-07"/>
+    <nuclide name="Gd156" ao="7.98718337741297e-09"/>
     <nuclide name="Gd157" ao="4.865379817976642e-10"/>
-    <nuclide name="I135" ao="8.523326262987082e-09"/>
-    <nuclide name="U234" ao="1.004449677662597e-05"/>
-    <nuclide name="U235" ao="0.0010175799065569445"/>
-    <nuclide name="U238" ao="0.02213426568393913"/>
-    <nuclide name="Xe135" ao="4.86982078246298e-09"/>
-    <nuclide name="Xe136" ao="1.6938385702297322e-06"/>
+    <nuclide name="I135" ao="8.523326262987085e-09"/>
+    <nuclide name="U234" ao="1.0044496776625974e-05"/>
+    <nuclide name="U235" ao="0.0010175799065569448"/>
+    <nuclide name="U238" ao="0.022134265683939135"/>
+    <nuclide name="Xe135" ao="4.869820782462982e-09"/>
+    <nuclide name="Xe136" ao="1.6938385702297311e-06"/>
   </material>
   <material id="7" depletable="true" volume="0.06674732823364922" temperature="293.6">
     <density units="sum"/>
     <nuclide name="O16" ao="0.046295399999999994"/>
     <nuclide name="O17" ao="0.00011276839999999999"/>
-    <nuclide name="Cs135" ao="4.365851597102055e-07"/>
-    <nuclide name="Gd156" ao="7.885461639644807e-09"/>
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+    <nuclide name="Cs135" ao="4.124689390009502e-07"/>
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+    <nuclide name="Xe135" ao="5.171435873222659e-09"/>
+    <nuclide name="Xe136" ao="4.423753279029924e-07"/>
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+    <nuclide name="Cs135" ao="4.559453986372943e-07"/>
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@@ -474,68 +474,68 @@
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+    <nuclide name="Gd157" ao="4.3278620054638127e-10"/>
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+    <nuclide name="U238" ao="0.02213419851406878"/>
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     <nuclide name="O17" ao="0.00011276839999999999"/>
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+    <nuclide name="Cs135" ao="4.758524423192085e-07"/>
     <nuclide name="Gd156" ao="7.047102473389166e-09"/>
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+    <nuclide name="Gd157" ao="4.2900777161502475e-10"/>
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     <nuclide name="U234" ao="1.004490745184468e-05"/>
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+    <nuclide name="Xe135" ao="4.972382302373322e-09"/>
+    <nuclide name="Xe136" ao="1.4220785344272178e-06"/>
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+    <nuclide name="Cs135" ao="4.6746885907144784e-07"/>
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+    <nuclide name="Xe135" ao="5.177831769145723e-09"/>
+    <nuclide name="Xe136" ao="1.4072673436878664e-06"/>
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+    <nuclide name="Cs135" ao="4.317484593765454e-07"/>
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-    <nuclide name="Xe135" ao="4.985811384270827e-09"/>
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@@ -543,37 +543,37 @@
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+    <nuclide name="Gd156" ao="7.934623609364994e-09"/>
+    <nuclide name="Gd157" ao="4.037668757136324e-10"/>
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+    <nuclide name="Cs135" ao="4.552489408257275e-07"/>
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@@ -582,194 +582,194 @@
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-    <nuclide name="Xe136" ao="1.8535025407324627e-06"/>
+    <nuclide name="Cs135" ao="4.6621088555426313e-07"/>
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+    <nuclide name="Xe136" ao="1.8535025407324654e-06"/>
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+    <nuclide name="Cs135" ao="4.5766121557221326e-07"/>
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+    <nuclide name="Gd157" ao="3.509450654334916e-10"/>
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+    <nuclide name="I135" ao="9.601996875186724e-09"/>
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@@ -777,219 +777,219 @@
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-    <nuclide name="Cs135" ao="4.6223836650122475e-07"/>
-    <nuclide name="Gd156" ao="7.953476976385664e-09"/>
-    <nuclide name="Gd157" ao="4.1027175087519965e-10"/>
-    <nuclide name="I135" ao="9.796423506518835e-09"/>
-    <nuclide name="U234" ao="1.0044187649341062e-05"/>
+    <nuclide name="Cs135" ao="4.622383665012244e-07"/>
+    <nuclide name="Gd156" ao="7.953476976385668e-09"/>
+    <nuclide name="Gd157" ao="4.102717508751997e-10"/>
+    <nuclide name="I135" ao="9.796423506518833e-09"/>
+    <nuclide name="U234" ao="1.0044187649341055e-05"/>
     <nuclide name="U235" ao="0.0010170353834242176"/>
-    <nuclide name="U238" ao="0.022134372559487282"/>
-    <nuclide name="Xe135" ao="5.0991030899242805e-09"/>
-    <nuclide name="Xe136" ao="1.7121460733075797e-06"/>
+    <nuclide name="U238" ao="0.02213437255948731"/>
+    <nuclide name="Xe135" ao="5.099103089924277e-09"/>
+    <nuclide name="Xe136" ao="1.7121460733075808e-06"/>
   </material>
   <material id="70" depletable="true" volume="0.06674732823364922" temperature="293.6">
     <density units="sum"/>
     <nuclide name="O16" ao="0.046295399999999994"/>
     <nuclide name="O17" ao="0.00011276839999999999"/>
-    <nuclide name="Cs135" ao="4.664997159187979e-07"/>
-    <nuclide name="Gd156" ao="9.025781278455481e-09"/>
-    <nuclide name="Gd157" ao="3.190701703279217e-10"/>
-    <nuclide name="I135" ao="1.4711477916054572e-08"/>
-    <nuclide name="U234" ao="1.0043737061563706e-05"/>
-    <nuclide name="U235" ao="0.0010106766373031348"/>
-    <nuclide name="U238" ao="0.02213424099107004"/>
-    <nuclide name="Xe135" ao="5.458886745013372e-09"/>
-    <nuclide name="Xe136" ao="2.0466796921687864e-06"/>
+    <nuclide name="Cs135" ao="4.664997159187976e-07"/>
+    <nuclide name="Gd156" ao="9.025781278455473e-09"/>
+    <nuclide name="Gd157" ao="3.190701703279215e-10"/>
+    <nuclide name="I135" ao="1.4711477916054554e-08"/>
+    <nuclide name="U234" ao="1.0043737061563701e-05"/>
+    <nuclide name="U235" ao="0.001010676637303134"/>
+    <nuclide name="U238" ao="0.022134240991070024"/>
+    <nuclide name="Xe135" ao="5.458886745013367e-09"/>
+    <nuclide name="Xe136" ao="2.0466796921687826e-06"/>
   </material>
   <material id="71" depletable="true" volume="0.06674732823364922" temperature="293.6">
     <density units="sum"/>
     <nuclide name="O16" ao="0.046295399999999994"/>
     <nuclide name="O17" ao="0.00011276839999999999"/>
     <nuclide name="Cs135" ao="4.6163611872342463e-07"/>
-    <nuclide name="Gd156" ao="8.092676337515914e-09"/>
-    <nuclide name="Gd157" ao="4.0155978871991965e-10"/>
+    <nuclide name="Gd156" ao="8.092676337515918e-09"/>
+    <nuclide name="Gd157" ao="4.015597887199194e-10"/>
     <nuclide name="I135" ao="1.1255710201354816e-08"/>
-    <nuclide name="U234" ao="1.0044080156464483e-05"/>
+    <nuclide name="U234" ao="1.0044080156464456e-05"/>
     <nuclide name="U235" ao="0.0010160767932805275"/>
     <nuclide name="U238" ao="0.022134404858133214"/>
-    <nuclide name="Xe135" ao="6.1065455616234985e-09"/>
-    <nuclide name="Xe136" ao="1.7613053571588805e-06"/>
+    <nuclide name="Xe135" ao="6.106545561623501e-09"/>
+    <nuclide name="Xe136" ao="1.761305357158882e-06"/>
   </material>
   <material id="72" depletable="true" volume="0.06674732823364922" temperature="293.6">
     <density units="sum"/>
     <nuclide name="O16" ao="0.046295399999999994"/>
     <nuclide name="O17" ao="0.00011276839999999999"/>
-    <nuclide name="Cs135" ao="4.5571123718376045e-07"/>
-    <nuclide name="Gd156" ao="6.928887839072172e-09"/>
-    <nuclide name="Gd157" ao="4.3753171369940084e-10"/>
-    <nuclide name="I135" ao="8.934890686722866e-09"/>
-    <nuclide name="U234" ao="1.0044610174441688e-05"/>
-    <nuclide name="U235" ao="0.0010236806448679259"/>
-    <nuclide name="U238" ao="0.022134444472317126"/>
-    <nuclide name="Xe135" ao="5.225774688291077e-09"/>
+    <nuclide name="Cs135" ao="4.5571123718376113e-07"/>
+    <nuclide name="Gd156" ao="6.928887839072173e-09"/>
+    <nuclide name="Gd157" ao="4.3753171369940074e-10"/>
+    <nuclide name="I135" ao="8.934890686722868e-09"/>
+    <nuclide name="U234" ao="1.004461017444169e-05"/>
+    <nuclide name="U235" ao="0.0010236806448679252"/>
+    <nuclide name="U238" ao="0.02213444447231712"/>
+    <nuclide name="Xe135" ao="5.2257746882910765e-09"/>
     <nuclide name="Xe136" ao="1.3609040886582337e-06"/>
   </material>
   <material id="73" volume="0.017528298008244847" temperature="293.6">
diff --git a/tests/regression_tests/deplete_with_transport/test_reference.h5 b/tests/regression_tests/deplete_with_transport/test_reference.h5
index e8478250be6..b54bbaa534e 100644
Binary files a/tests/regression_tests/deplete_with_transport/test_reference.h5 and b/tests/regression_tests/deplete_with_transport/test_reference.h5 differ
diff --git a/tests/unit_tests/test_config.py b/tests/unit_tests/test_config.py
index 242c59b5e23..ea2a8ec416a 100644
--- a/tests/unit_tests/test_config.py
+++ b/tests/unit_tests/test_config.py
@@ -94,10 +94,3 @@ def test_config_warning_nonexistent_path(tmp_path):
         openmc.config['chain_file'] = bad_path
 
 
-def test_config_chain_side_effect(tmp_path):
-    """Test that modifying chain_file clears decay data caches."""
-    chain_file = tmp_path / "chain.xml"; chain_file.touch()
-    decay._DECAY_ENERGY['U235'] = (1.0, 2.0)
-    decay._DECAY_PHOTON_ENERGY['PU239'] = {}
-    openmc.config['chain_file'] = chain_file
-    assert not decay._DECAY_ENERGY and not decay._DECAY_PHOTON_ENERGY
diff --git a/tests/unit_tests/test_data_misc.py b/tests/unit_tests/test_data_misc.py
index b65c704af8e..d02e30c5f6e 100644
--- a/tests/unit_tests/test_data_misc.py
+++ b/tests/unit_tests/test_data_misc.py
@@ -135,11 +135,12 @@ def test_zam():
         openmc.data.zam('Am242-m1')
 
 def test_half_life():
-    assert openmc.data.half_life('H2') is None
-    assert openmc.data.half_life('U235') == pytest.approx(2.22102e16)
-    assert openmc.data.half_life('Am242') == pytest.approx(57672.0)
-    assert openmc.data.half_life('Am242_m1') == pytest.approx(4449622000.0)
-    assert openmc.data.decay_constant('H2') == 0.0
-    assert openmc.data.decay_constant('U235') == pytest.approx(log(2.0)/2.22102e16)
-    assert openmc.data.decay_constant('Am242') == pytest.approx(log(2.0)/57672.0)
+    with openmc.config.patch('chain_file', None):
+        assert openmc.data.half_life('H2') is None
+        assert openmc.data.half_life('U235') == pytest.approx(2.22102e16)
+        assert openmc.data.half_life('Am242') == pytest.approx(57672.0)
+        assert openmc.data.half_life('Am242_m1') == pytest.approx(4449622000.0)
+        assert openmc.data.decay_constant('H2') == 0.0
+        assert openmc.data.decay_constant('U235') == pytest.approx(log(2.0)/2.22102e16)
+        assert openmc.data.decay_constant('Am242') == pytest.approx(log(2.0)/57672.0)
     assert openmc.data.decay_constant('Am242_m1') == pytest.approx(log(2.0)/4449622000.0)
diff --git a/tests/unit_tests/test_deplete_integrator.py b/tests/unit_tests/test_deplete_integrator.py
index b1d2cb950eb..e28b74fb6c1 100644
--- a/tests/unit_tests/test_deplete_integrator.py
+++ b/tests/unit_tests/test_deplete_integrator.py
@@ -44,6 +44,8 @@ def test_results_save(run_in_tmpdir):
 
     # Mock geometry
     op = MagicMock()
+    
+    op.chain = dummy_operator.TestChain()
 
     # Avoid DummyOperator thinking it's doing a restart calculation
     op.prev_res = None