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Adding reaction types to several different kinds of data.
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‎ContinuousEnergyNeutron.ipynb‎

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"ZA = 5010\n",
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"display(ZA)"
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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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"## Reaction Types\n",
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"This not a complete list of reaction numbers. For more information consult the MCNP manual and the ENDF-6 format manual.\n",
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"\n",
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"| MT | FM | Microscopic Cross-Section Description | \n",
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"| -- | -- | -- | \n",
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"| 1 | -1 | Total | \n",
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"| 2 | -3 | Elastic | \n",
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"| 16 | | $(n,2n)$ | \n",
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"| 17 | | $(n,3n)$ | \n",
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"| 18 | | Total fission $(n,fx)$ | \n",
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"| | -6 | Total fission cross section. [1] | \n",
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"| | -7 | Nubar (prompt or total) [2] | \n",
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"| | -8 | Fission Q | \n",
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"| 19 | | $(n,f)$ | \n",
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"| 20 | | $(n,n'f)$ | \n",
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"| 21 | | $(n,2nf)$ | \n",
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"| 22 | | $(n,n'\\alpha)$ | \n",
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"| 28 | | $(n,n'p)$ | \n",
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"| 32 | | $(n,n'd)$ | \n",
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"| 33 | | $(n,n't)$ | \n",
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"| 38 | | $(n,3nf)$ | \n",
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"| 51 | | $(n,n')$ to 1st excited state | \n",
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"| 52 | | $(n,n')$ to 2nd excited state | \n",
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"| $\\cdots$ | | $\\cdots$ | \n",
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"| 90 | | $(n,n')$ to 40th excited state | \n",
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"| 91 | | $(n,n')$ to continuum | \n",
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"| 101 | -2 | Absorption | \n",
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"| 102 | | $(n,\\gamma)$ | \n",
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"| 103 | | $(n,p)$ | \n",
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"| 104 | | $(n,d)$ | \n",
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"| 105 | | $(n,t)$ | \n",
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"| 106 | | $(n,3He)$ | \n",
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"| 107 | | $(n,\\alpha)$ | \n",
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"| 202 | -5 | Total photon production | \n",
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"| 203 | | Total proton production | \n",
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"| 204 | | Total deuterium production | \n",
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"| 205 | | Total tritium production | \n",
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"| 206 | | Total 3He production\n",
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"| 207 | | Total alpha production | \n",
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"| 301 | -4 | Average heating numbers (MeV/collision) | \n",
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"\n",
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"**Notes**\n",
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"1. `FM=-6` equal to MT=18 if MT=18 exists; otherwise equal to the sum of MTs 19, 20, 21, and 38.\n",
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"2. `MT=101`, `FM=-2` sum of `MT=102--117` neutron disappearance; does not include fission.\n",
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"3. `FM=-8` used in print table 98, but not plots.\n"
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]
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}
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],
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"metadata": {

‎Electron.ipynb‎

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"ZA = 1000\n",
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"display(ZA)"
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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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"## Reaction Types\n",
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"This not a complete list of reaction numbers. For more information consult the MCNP manual and the ENDF-6 format manual.\n",
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"\n",
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"| MT | FM | Microscopic Cross-Section Description | \n",
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"| -- | -- | -- | \n",
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"| | 1 | $de/dx$ electron collision stopping power | \n",
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"| | 2 | $de/dx$ electron radiative stopping power | \n",
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"| | 3 | $de/dx$ total electron stopping power | \n",
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"| | 4 | electron range | \n",
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"| | 5 | electron radiation yield | \n",
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"| | 6 | relativistic $\\beta^2$ | \n",
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"| | 7 | stopping power density correction | \n",
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"| | 8 | ratio of rad/col stopping powers | \n",
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"| | 9 | $drange$ | \n",
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"| | 10 | $dyield$ | \n",
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"| | 11 | $rng$ array values | \n",
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"| | 12 | $qav$ array values | \n",
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"| | 13 | $ear$ array values | \n"
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]
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}
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],
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"metadata": {

‎NeutronPhoton.ipynb‎

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"ZA = 1001\n",
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"display()"
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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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"## Reaction Types\n",
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"This not a complete list of reaction numbers. For more information consult the MCNP manual and the ENDF-6 format manual.\n",
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"\n",
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"| MT | FM | Microscopic Cross-Section Description | \n",
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"| -- | -- | -- | \n",
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"| 1 | -1 | Total cross section | \n",
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"| 18 | -2 | Fission cross section | \n",
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"| | -3 | Nubar data | \n",
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"| | -4 | Fission chi data | \n",
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"| 101 | -5 | Absorption cross section | \n",
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"| | -6 | Stopping powers | \n",
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"| | -7 | Momentum transfers | \n",
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"| 202 | | Photon production | \n",
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"| 301 | | Heating number | \n",
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"| 318 | | Fission Q | \n",
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"| 401 | | Heating number times total cross section | "
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]
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}
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],
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"metadata": {

‎Photoatomic.ipynb‎

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"ZA = 1000\n",
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"display(ZA)"
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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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"## Reaction Types\n",
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"This not a complete list of reaction numbers. For more information consult the MCNP manual and the ENDF-6 format manual.\n",
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"\n",
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" | MT | FM | Microscopic Cross-Section Description | \n",
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" | -- | -- | -- | \n",
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" | 501 | -5 | Total | \n",
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" | 504 | -1 | Incoherent (Compton + Form Factor) | \n",
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" | 502 | -2 | Coherent (Thomson + Form Factor) | \n",
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" | 522 | -3 | Photoelectric with fluorescence | \n",
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" | 516 | -4 | Pair production | \n",
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" | 301 | -6 | Heating number | \n"
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]
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}
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],
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"metadata": {

‎Photonuclear.ipynb‎

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"ZA = 1002\n",
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"display()"
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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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"## Reaction Types\n",
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"This not a complete list of reaction numbers. For more information consult the MCNP manual and the ENDF-6 format manual.\n",
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"\n",
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"| MT | FM | Microscopic Cross-Section Description | \n",
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"| -- | -- | -- | \n",
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"| | 1 | Total | \n",
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"| | 2 | Non-elastic | \n",
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"| | 3 | Elastic | \n",
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"| | 4 | Heating | \n",
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"| | 5 | Other | \n",
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"| | 100x | Neutron production from reaction $x$ | \n",
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"| | 200x | Photon production from reaction $x$ | \n",
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"| | 900x | Proton production from reaction $x$ | \n"
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]
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}
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],
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"metadata": {

‎ThermalScattering.ipynb‎

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"material = 'h-h2o' \n",
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"display(material)"
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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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"## Reaction Types\n",
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"This not a complete list of reaction numbers. For more information consult the MCNP manual and the ENDF-6 format manual.\n",
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"\n",
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" | MT | FM | Microscopic Cross-Section Description | \n",
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" | -- | -- | -- | \n",
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" | 1 | | Total cross section | \n",
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" | 2 | | Elastic scattering cross section | \n",
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" | 4 | | Inelastic scattering cross section | "
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]
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}
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],
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"metadata": {

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