@@ -277,6 +277,15 @@ ignored for all run modes other than "eigenvalue".
277277
278278 *Default *: 1
279279
280+ ------------------------------
281+ ``<ifp_n_generation> `` Element
282+ ------------------------------
283+
284+ The ``<ifp_n_generation> `` element indicates the number of generations to
285+ consider for the Iterated Fission Probability method.
286+
287+ *Default *: 10
288+
280289----------------------
281290``<inactive> `` Element
282291----------------------
@@ -402,7 +411,25 @@ then, OpenMC will only use up to the :math:`P_1` data.
402411``<max_history_splits> `` Element
403412--------------------------------
404413
405- The ``<max_history_splits> `` element indicates the number of times a particle can split during a history.
414+ The ``<max_history_splits> `` element indicates the number of times a particle
415+ can split during a history.
416+
417+ *Default *: 1000
418+
419+ -----------------------------
420+ ``<max_secondaries> `` Element
421+ -----------------------------
422+
423+ The ``<max_secondaries> `` element indicates the maximum secondary bank size.
424+
425+ *Default *: 10000
426+
427+ ------------------------
428+ ``<max_tracks> `` Element
429+ ------------------------
430+
431+ The ``<max_tracks> `` element indicates the maximum number of tracks written to a
432+ track file (per MPI process).
406433
407434 *Default *: 1000
408435
@@ -1378,6 +1405,15 @@ has the following attributes/sub-elements:
13781405 for fixed source and small criticality calculations, but is very
13791406 optimistic for highly coupled full-core reactor problems.
13801407
1408+ -------------------------------------
1409+ ``<uniform_source_sampling> `` Element
1410+ -------------------------------------
1411+
1412+ The ``<uniform_source_sampling> `` element indicates whether to sample among
1413+ multiple sources uniformly, applying their strengths as weights to sampled
1414+ particles.
1415+
1416+ *Default *: False
13811417
13821418------------------------
13831419``<ufs_mesh> `` Element
@@ -1390,6 +1426,16 @@ Agency Monte Carlo Performance Benchmark Problem," Proceedings of *Physor 2012*,
13901426Knoxville, TN (2012). The mesh should cover all possible fissionable materials
13911427in the problem and is specified using a :ref: `mesh_element `.
13921428
1429+ -------------------------------
1430+ ``<use_decay_photons> `` Element
1431+ -------------------------------
1432+
1433+ The ``<use_decay_photons> `` element indicates whether to produce decay photons
1434+ from neutron reactions instead of prompt photons. This is used in conjunction
1435+ with the direct 1-step method for shutdown dose rate calculations.
1436+
1437+ *Default *: False
1438+
13931439.. _verbosity :
13941440
13951441-----------------------
@@ -1620,3 +1666,21 @@ following sub-elements/attributes:
16201666
16211667 The ``weight_windows_file `` element has no attributes and contains the path to
16221668 a weight windows HDF5 file to load during simulation initialization.
1669+
1670+ -------------------------------
1671+ ``<weight_windows_on> `` Element
1672+ -------------------------------
1673+
1674+ The ``weight_windows_on `` element indicates whether weight windows are
1675+ enabled.
1676+
1677+ *Default *: False
1678+
1679+ ----------------------------------
1680+ ``<write_initial_source> `` Element
1681+ ----------------------------------
1682+
1683+ The ``write_initial_source `` element indicates whether to write the initial
1684+ source distribution to file.
1685+
1686+ *Default *: False
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