Differences in 0.11 and 0.12+ Depletion chain files?

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Hello,

I am analyzing some results between a benchmark with depletion analysis. I noticed that some actinides such as Pu244, Cm244 etc… resulted in very different values between chains and between Serpent 2 results. On further analysis and comparison of 0.11 and 0.12 endfb71_pwr.xml chains (Depletion Chains | OpenMC), there are a different number of reactions in the isotopes I mentioned. Specifically, the fission reaction is missing in the 0.11 version.

My question is more out of curiosity rather than actual concern as I do my analysis - I am wondering if I am overlooking anything here in this conclusion or if the fission reaction is included elsewhere.

Pu244 v0.11:

  <nuclide name="Pu244" half_life="2559320000000000.0" decay_modes="2" decay_energy="4879278.93" reactions="4">
    <decay type="sf" target="Pu244" branching_ratio="0.00125"/>
    <decay type="alpha" target="U240" branching_ratio="0.99875"/>
    <reaction type="(n,2n)" Q="-6021270.0" target="Pu243"/>
    <reaction type="(n,3n)" Q="-11055500.0" target="Pu242"/>
    <reaction type="(n,4n)" Q="-17365200.0" target="Pu241"/>
    <reaction type="(n,gamma)" Q="4770800.0" target="Pu245"/>
  </nuclide>

Pu244 v0.12+

  <nuclide name="Pu244" half_life="2559320000000000.0" decay_modes="2" decay_energy="4879278.93" reactions="5">
    <decay type="sf" target="Pu244" branching_ratio="0.00125"/>
    <decay type="alpha" target="U240" branching_ratio="0.99875"/>
    <source type="discrete" particle="photon">
      <parameters>3249.799 13608.41 14105.81 17112.84 20361.23 44000.0 3.0218332164013212e-18 8.580695830001468e-18 1.114668806087841e-18 9.311997901234438e-18 2.048614025844678e-18 7.820541966438877e-20</parameters>
    </source>
    <source type="discrete" particle="alpha">
      <parameters>4546000.0 4589000.0 5.247583922188066e-17 2.1801817738575162e-16</parameters>
    </source>
    <source type="discrete" particle="fragment">
      <parameters> </parameters>
    </source>
    <source type="discrete" particle="neutron">
      <parameters> </parameters>
    </source>
    <source type="discrete" particle="electron">
      <parameters>496.9974 1191.341 2509.945 10199.03 13522.03 16877.17 22242.6 38452.0 42559.2 43836.2 43980.3 1.613507710074958e-17 4.983286554491555e-18 5.11727283724112e-17 1.2503968130134298e-17 6.376622562101356e-18 7.654356400951407e-19 3.830734231953109e-17 1.0495165136050558e-17 2.886170480122043e-18 6.29710070662568e-19 1.0495167844376132e-19</parameters>
    </source>
    <reaction type="(n,2n)" Q="-6021270.0" target="Pu243"/>
    <reaction type="(n,3n)" Q="-11055500.0" target="Pu242"/>
    <reaction type="(n,4n)" Q="-17365200.0" target="Pu241"/>
    <reaction type="(n,gamma)" Q="4770800.0" target="Pu245"/>
    <reaction type="fission" Q="199292800.0"/>
    <neutron_fission_yields parent="Cm246"/>
  </nuclide>

Thank you,
Jonathon