OpenMC/tests/regression_tests/trigger_batch_interval/tallies.xml

<?xml version="1.0"?>
<tallies>

  <tally id="1">
    <nuclides>Pu239 total</nuclides>
    <scores>total absorption fission scatter</scores>
  </tally>

  <tally id="2">
    <nuclides>Pu239</nuclides>
    <scores>total absorption fission scatter</scores>
  </tally>

</tallies>
Added new test in test suite to check for <nuclides>all</nuclides> with void material. 2014-05-15 23:39:46 -04:00			`<?xml version="1.0"?>`
			`<tallies>`

			`<tally id="1">`
Fix failing tests that were using "all" in tally nuclides 2022-02-23 06:35:05 -06:00			`<nuclides>Pu239 total</nuclides>`
Added new test in test suite to check for <nuclides>all</nuclides> with void material. 2014-05-15 23:39:46 -04:00			`<scores>total absorption fission scatter</scores>`
			`</tally>`

Updated test_tally_nuclides to include a tally containing a <nuclide> filter with only one nuclide. 2014-06-02 21:12:12 -04:00			`<tally id="2">`
Added full openmc.data package and hooks in code 2016-05-13 15:57:39 -05:00			`<nuclides>Pu239</nuclides>`
Updated test_tally_nuclides to include a tally containing a <nuclide> filter with only one nuclide. 2014-06-02 21:12:12 -04:00			`<scores>total absorption fission scatter</scores>`
			`</tally>`

Added new test in test suite to check for <nuclides>all</nuclides> with void material. 2014-05-15 23:39:46 -04:00			`</tallies>`