Keyword:FUEL

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FUEL n1
is(j) atoms(j) j=1,n1


This keyword allows the input of the number, n1 of nuclides and the name, is(j) and the number of atoms, atoms(j) for each nuclide. The name is specified using the standard format e.g. Te129m. The specification of nuclides is essential if the materials to be irradiated do not have the natural isotopic abundance. If different values are required then FUEL should be used. The total mass of input material is calculated from the amounts of the nuclides input.

Note that FUEL and MASS must not both be used in a particular case. If FUEL is used for a run in which an inventory is calculated then the density of the material must be specified using DENSITY.

An example where an enriched uranium fuel is being specified as input material would be:

< -- Control phase -- >
...
FISPACT
* Title of the simulation
< -- Initial phase -- > 
FUEL 3
U234 9.04845E+18
U235 9.56210E+20
U238 2.19628E+22
...
< -- Inventory phase -- > 
...