mirror of
https://github.com/openmc-dev/openmc.git
synced 2026-07-28 22:26:08 -04:00
added example notebook for covariance module
This commit is contained in:
Isaac Meyer
parent
1963fbe60b
commit
416a89c785
3 changed files with 24 additions and 150 deletions
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@ -24,6 +24,7 @@ Basic Usage
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triso
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candu
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nuclear-data
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nuclear-data-resonance-covariance
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------------------------------------
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Multi-Group Cross Section Generation
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13
docs/source/examples/nuclear-data-resonance-covariance.rst
Normal file
13
docs/source/examples/nuclear-data-resonance-covariance.rst
Normal file
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@ -0,0 +1,13 @@
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.. _notebook_nuclear_data_resonance_covariance:
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==================================
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Nuclear Data: Resonance Covariance
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==================================
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.. only:: html
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.. notebook:: ../../../examples/jupyter/nuclear-data-resonance-covariance.ipynb
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.. only:: latex
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IPython notebooks must be viewed in the online HTML documentation.
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@ -28,7 +28,9 @@
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{
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"cell_type": "code",
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"execution_count": 1,
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"metadata": {},
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"metadata": {
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"collapsed": false
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},
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"outputs": [
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{
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"data": {
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@ -132,7 +134,9 @@
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{
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"cell_type": "code",
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"execution_count": 2,
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"metadata": {},
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"metadata": {
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"collapsed": false
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},
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"outputs": [],
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"source": [
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"%matplotlib inline\n",
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@ -153,33 +157,11 @@
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{
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"cell_type": "code",
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"execution_count": 3,
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"metadata": {},
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"metadata": {
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"collapsed": true
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},
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"outputs": [],
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"source": [
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<<<<<<< HEAD
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"# Instantiate some Nuclides\n",
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"h1 = openmc.Nuclide('H1')\n",
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"o16 = openmc.Nuclide('O16')\n",
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"u235 = openmc.Nuclide('U235')\n",
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"u238 = openmc.Nuclide('U238')\n",
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"zr90 = openmc.Nuclide('Zr90')"
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]
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},
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{
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"cell_type": "markdown",
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"metadata": {},
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"source": [
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"With the nuclides we defined, we will now create a material for the homogeneous medium."
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]
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},
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{
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"cell_type": "code",
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"execution_count": 4,
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"metadata": {},
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"outputs": [],
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"source": [
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=======
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>>>>>>> upstream/develop
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"# Instantiate a Material and register the Nuclides\n",
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"inf_medium = openmc.Material(name='moderator')\n",
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"inf_medium.set_density('g/cc', 5.)\n",
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@ -199,15 +181,10 @@
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},
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{
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"cell_type": "code",
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<<<<<<< HEAD
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"execution_count": 5,
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"metadata": {},
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=======
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"execution_count": 4,
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"metadata": {
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"collapsed": true
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},
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>>>>>>> upstream/develop
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"outputs": [],
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"source": [
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"# Instantiate a Materials collection and export to XML\n",
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@ -224,15 +201,10 @@
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},
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{
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"cell_type": "code",
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<<<<<<< HEAD
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"execution_count": 6,
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"metadata": {},
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=======
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"execution_count": 5,
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"metadata": {
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"collapsed": true
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},
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>>>>>>> upstream/develop
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"outputs": [],
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"source": [
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"# Instantiate boundary Planes\n",
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@ -251,15 +223,10 @@
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},
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{
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"cell_type": "code",
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<<<<<<< HEAD
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"execution_count": 7,
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"metadata": {},
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=======
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"execution_count": 6,
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"metadata": {
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"collapsed": false
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},
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>>>>>>> upstream/develop
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"outputs": [],
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"source": [
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"# Instantiate a Cell\n",
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@ -281,15 +248,10 @@
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},
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{
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"cell_type": "code",
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<<<<<<< HEAD
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"execution_count": 8,
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"metadata": {},
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=======
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"execution_count": 7,
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"metadata": {
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"collapsed": true
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},
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>>>>>>> upstream/develop
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"outputs": [],
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"source": [
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"# Create root universe\n",
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@ -305,15 +267,10 @@
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},
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{
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"cell_type": "code",
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<<<<<<< HEAD
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"execution_count": 9,
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"metadata": {},
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=======
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"execution_count": 8,
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"metadata": {
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"collapsed": false
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},
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>>>>>>> upstream/develop
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"outputs": [],
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"source": [
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"# Create Geometry and set root Universe\n",
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@ -332,15 +289,10 @@
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},
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{
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"cell_type": "code",
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<<<<<<< HEAD
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"execution_count": 10,
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"metadata": {},
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=======
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"execution_count": 9,
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"metadata": {
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"collapsed": true
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},
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>>>>>>> upstream/develop
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"outputs": [],
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"source": [
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"# OpenMC simulation parameters\n",
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@ -373,15 +325,10 @@
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},
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{
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"cell_type": "code",
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<<<<<<< HEAD
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"execution_count": 11,
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"metadata": {},
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=======
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"execution_count": 10,
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"metadata": {
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"collapsed": false
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},
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>>>>>>> upstream/develop
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"outputs": [],
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"source": [
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"# Instantiate a 2-group EnergyGroups object\n",
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@ -417,15 +364,10 @@
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},
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{
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"cell_type": "code",
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<<<<<<< HEAD
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"execution_count": 12,
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"metadata": {},
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=======
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"execution_count": 11,
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"metadata": {
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"collapsed": false
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},
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>>>>>>> upstream/develop
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"outputs": [],
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"source": [
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"# Instantiate a few different sections\n",
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@ -447,15 +389,10 @@
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},
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{
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"cell_type": "code",
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<<<<<<< HEAD
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"execution_count": 13,
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"metadata": {},
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=======
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"execution_count": 12,
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"metadata": {
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"collapsed": false
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},
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>>>>>>> upstream/develop
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"outputs": [
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{
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"data": {
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@ -493,29 +430,18 @@
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},
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{
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"cell_type": "code",
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<<<<<<< HEAD
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"execution_count": 14,
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"metadata": {},
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=======
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"execution_count": 13,
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"metadata": {
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"collapsed": false
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},
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>>>>>>> upstream/develop
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"outputs": [
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{
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"name": "stderr",
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"output_type": "stream",
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"text": [
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<<<<<<< HEAD
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"/home/icmeyer/miniconda3/lib/python3.6/site-packages/openmc-0.9.0-py3.6-linux-x86_64.egg/openmc/mixin.py:61: IDWarning: Another CellFilter instance already exists with id=3.\n",
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" warn(msg, IDWarning)\n",
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"/home/icmeyer/miniconda3/lib/python3.6/site-packages/openmc-0.9.0-py3.6-linux-x86_64.egg/openmc/mixin.py:61: IDWarning: Another EnergyFilter instance already exists with id=4.\n",
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=======
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"/home/romano/openmc/openmc/mixin.py:61: IDWarning: Another CellFilter instance already exists with id=3.\n",
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" warn(msg, IDWarning)\n",
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"/home/romano/openmc/openmc/mixin.py:61: IDWarning: Another EnergyFilter instance already exists with id=4.\n",
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>>>>>>> upstream/develop
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" warn(msg, IDWarning)\n"
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]
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}
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},
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{
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"cell_type": "code",
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<<<<<<< HEAD
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"execution_count": null,
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"metadata": {},
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"outputs": [],
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=======
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"execution_count": 14,
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"metadata": {
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"collapsed": false
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@ -702,7 +623,6 @@
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"output_type": "execute_result"
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}
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],
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>>>>>>> upstream/develop
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"source": [
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"# Run OpenMC\n",
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"openmc.run()"
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},
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{
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"cell_type": "code",
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<<<<<<< HEAD
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"execution_count": null,
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"metadata": {},
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=======
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"execution_count": 15,
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"metadata": {
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"collapsed": false
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},
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>>>>>>> upstream/develop
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"outputs": [],
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"source": [
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"# Load the last statepoint file\n",
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@ -755,15 +670,10 @@
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},
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{
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"cell_type": "code",
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<<<<<<< HEAD
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"execution_count": null,
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"metadata": {},
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=======
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"execution_count": 16,
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"metadata": {
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"collapsed": false
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},
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>>>>>>> upstream/develop
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"outputs": [],
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"source": [
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"# Load the tallies from the statepoint into each MGXS object\n",
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@ -795,11 +705,6 @@
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},
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{
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"cell_type": "code",
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<<<<<<< HEAD
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"execution_count": null,
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"metadata": {},
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"outputs": [],
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=======
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"execution_count": 17,
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"metadata": {
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"collapsed": false
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@ -822,7 +727,6 @@
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]
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}
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],
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>>>>>>> upstream/develop
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"source": [
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"total.print_xs()"
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]
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},
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{
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"cell_type": "code",
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"execution_count": null,
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"metadata": {},
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"outputs": [],
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=======
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"execution_count": 18,
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"metadata": {
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"collapsed": false
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"output_type": "execute_result"
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}
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],
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>>>>>>> upstream/develop
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"source": [
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"df = scattering.get_pandas_dataframe()\n",
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"df.head(10)"
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},
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{
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"cell_type": "code",
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<<<<<<< HEAD
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"execution_count": null,
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"metadata": {},
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=======
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"execution_count": 19,
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"metadata": {
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"collapsed": false
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},
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>>>>>>> upstream/develop
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"outputs": [],
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"source": [
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"absorption.export_xs_data(filename='absorption-xs', format='excel')"
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},
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{
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"cell_type": "code",
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<<<<<<< HEAD
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"execution_count": null,
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"metadata": {},
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=======
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"execution_count": 20,
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"metadata": {
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"collapsed": false
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},
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>>>>>>> upstream/develop
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"outputs": [],
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"source": [
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"total.build_hdf5_store(filename='mgxs', append=True)\n",
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},
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{
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"cell_type": "code",
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"execution_count": null,
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"metadata": {},
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"outputs": [],
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=======
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"execution_count": 21,
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"metadata": {
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"collapsed": false
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"output_type": "execute_result"
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}
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],
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>>>>>>> upstream/develop
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"source": [
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"# Use tally arithmetic to compute the difference between the total, absorption and scattering\n",
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"difference = total.xs_tally - absorption.xs_tally - scattering.xs_tally\n",
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},
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{
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"cell_type": "code",
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<<<<<<< HEAD
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"execution_count": null,
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"metadata": {},
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"outputs": [],
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=======
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"execution_count": 22,
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"metadata": {
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"collapsed": false
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"output_type": "execute_result"
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}
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],
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>>>>>>> upstream/develop
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"source": [
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"# Use tally arithmetic to compute the absorption-to-total MGXS ratio\n",
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"absorption_to_total = absorption.xs_tally / total.xs_tally\n",
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},
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{
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"cell_type": "code",
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<<<<<<< HEAD
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"execution_count": null,
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"metadata": {},
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"outputs": [],
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=======
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"execution_count": 23,
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"metadata": {
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"collapsed": false
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"output_type": "execute_result"
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}
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],
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>>>>>>> upstream/develop
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"source": [
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"# Use tally arithmetic to compute the scattering-to-total MGXS ratio\n",
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"scattering_to_total = scattering.xs_tally / total.xs_tally\n",
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},
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{
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"cell_type": "code",
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<<<<<<< HEAD
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"execution_count": null,
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"metadata": {},
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"outputs": [],
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=======
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"execution_count": 24,
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"metadata": {
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"collapsed": false
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"output_type": "execute_result"
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}
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],
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>>>>>>> upstream/develop
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"source": [
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"# Use tally arithmetic to ensure that the absorption- and scattering-to-total MGXS ratios sum to unity\n",
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"sum_ratio = absorption_to_total + scattering_to_total\n",
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"name": "python",
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"nbconvert_exporter": "python",
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"pygments_lexer": "ipython3",
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<<<<<<< HEAD
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"version": "3.6.3"
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=======
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"version": "3.6.0"
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>>>>>>> upstream/develop
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}
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},
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"nbformat": 4,
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"nbformat_minor": 1
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"nbformat_minor": 0
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}
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