@@ -20,6 +20,85 @@ source neutrons.
2020
2121 *Default *: None
2222
23+ -----------------------------
24+ ``<collision_track> `` Element
25+ -----------------------------
26+
27+ The ``<collision_track> `` element indicates to track information about particle
28+ collisions based on a set of criteria and store these events in a file named
29+ ``collision_track.h5 ``. This file records details such as the position of the
30+ interaction, direction of the incoming particle, incident energy and deposited
31+ energy, weight, time of the interaction, and the delayed neutron group (0 for
32+ prompt neutrons). Additional information such as the cell ID, material ID,
33+ universe ID, nuclide ZAID, particle type, and event MT number are also stored.
34+ Users can specify one or more criterion to filter collisions. If no criteria are
35+ specified, it defaults to tracking all collisions across the model.
36+
37+ .. warning ::
38+ Storing all collisions can be very memory intensive. For more targeted
39+ tracking, users can employ a variety of parameters such as ``cell_ids ``,
40+ ``reactions ``, ``universe_ids ``, ``material_ids ``, ``nuclides ``, and
41+ ``deposited_E_threshold `` to refine the selection of particle interactions
42+ to be banked.
43+
44+ This element can contain one or more of the following attributes or
45+ sub-elements:
46+
47+ :max_collisions:
48+ An integer indicating the maximum number of collisions to be banked per file.
49+
50+ *Default *: 1000
51+
52+ :max_collision_track_files:
53+ An integer indicating the number of collision_track files to be used.
54+
55+ *Default *: 1
56+
57+ :mcpl:
58+ An optional boolean to enable MCPL _-format instead of the native HDF5-based
59+ format. If activated, the output file name and type is changed to
60+ ``collision_track.mcpl ``.
61+
62+ *Default *: false
63+
64+ .. _MCPL : https://mctools.github.io/mcpl/mcpl.pdf
65+
66+ :cell_ids:
67+ A list of integers representing cell IDs to define specific cells in which
68+ collisions are to be banked.
69+
70+ *Default *: None
71+
72+ :universe_ids:
73+ A list of integers representing the universe IDs to define specific
74+ universes in which collisions are to be banked.
75+
76+ *Default *: None
77+
78+ :material_ids:
79+ A list of integers representing the material IDs to define specific
80+ materials in which collisions are to be banked.
81+
82+ *Default *: None
83+
84+ :nuclides:
85+ A list of strings representing the nuclide, to define specific
86+ define specific target nuclide collisions to be banked.
87+
88+ *Default *: None
89+
90+ :reactions:
91+ A list of integers representing the ENDF-6 format MT numbers or strings
92+ (e.g. (n,fission)) to define specific reaction types to be banked.
93+
94+ *Default *: None
95+
96+ :deposited_E_threshold:
97+ A float defining the minimum deposited energy per collision (in eV) to
98+ trigger banking.
99+
100+ *Default *: 0.0
101+
23102----------------------------------
24103``<confidence_intervals> `` Element
25104----------------------------------
@@ -178,6 +257,16 @@ history-based parallelism.
178257
179258 *Default *: false
180259
260+ --------------------------------
261+ ``<free_gas_threshold> `` Element
262+ --------------------------------
263+
264+ The ``<free_gas_threshold> `` element specifies the energy multiplier, expressed
265+ in units of :math: `kT`, that determines when the free gas scattering approach is
266+ used for elastic scattering. Values must be positive.
267+
268+ *Default *: 400.0
269+
181270-----------------------------------
182271``<generations_per_batch> `` Element
183272-----------------------------------
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