added prompt-nu-fission tally and reduced size of new MGXS types

This commit is contained in:
Sam Shaner 2016-07-05 14:43:40 -04:00
parent d3550389c9
commit 16dc3db6fa
10 changed files with 181 additions and 289 deletions

View file

@ -383,6 +383,9 @@
"* `ScatterMatrixXS`\n",
"* `NuScatterMatrixXS`\n",
"* `Chi`\n",
"* `ChiPrompt`\n",
"* `Velocity`\n",
"* `PromptNuFissionXS`\n",
"\n",
"These classes provide us with an interface to generate the tally inputs as well as perform post-processing of OpenMC's tally data to compute the respective multi-group cross sections. In this case, let's create the multi-group total, absorption and scattering cross sections with our 2-group structure."
]
@ -1181,7 +1184,7 @@
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@ -549,6 +549,9 @@
"* `ScatterMatrixXS` (`\"scatter matrix\"`)\n",
"* `NuScatterMatrixXS` (`\"nu-scatter matrix\"`)\n",
"* `Chi` (`\"chi\"`)\n",
"* `ChiPrompt` (`\"chi prompt\"`)\n",
"* `Velocity` (`\"velocity\"`)\n",
"* `PromptNuFissionXS` (`\"prompt-nu-fission\"`)\n",
"\n",
"In this case, let's create the multi-group cross sections needed to run an OpenMOC simulation to verify the accuracy of our cross sections. In particular, we will define `\"transport\"`, `\"nu-fission\"`, `'\"fission\"`, `\"nu-scatter matrix\"` and `\"chi\"` cross sections for our `Library`.\n",
"\n",
@ -1596,21 +1599,21 @@
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