Uranium Centrifuge Cascade Simulator
calculator will create an idealized Uranium Centrifuge Cascade from
values entered by the user. A Uranium Centrifuge cascade consists of a
number of centrifuges arranged in series and in parallel. A typical
cascade will consist of two sections: 1) The Enrichment section which
is designed to increase (enrich) the concentration of Uranium 235, in
stages, to a final concentration and 2) The Stripping section which is
designed to "strip", or remove, Uranium 235 from the waste products of
the enriching section. The user may specify the following variables
when creating a cascade:
1) Np : The desired final percentage of Uranium 235 in
the Product from the Enriching Section.
2) Nw : The desired final percentage of Uranium 235 in
the Waste (also called "tails") from the Stripping section.
3) Nf : The initial percentage of Uranium 235 in the
Feed to the cascade. In natural Uranium this percentage is about .71% .
4) P : The Product rate in multiples of 1576.8 kg/yr (the single-machine throughput).
assumes that the centrifuges are of the Countercurrent type, are 250
centimeters long, have radii of 25 cm, rotate at a peripheral speed of
600 meters per second, have a throughput (Feed and Waste+Product
takeoff) of .0001 kilograms per second, that the cut theta is .5, that
the average temperature of the centrifuge is 320 degrees Kelvin, that
the optimized separation factor has a value of 1.46, that the
separative power per centrifuge is approximately 38 kgSWU per year, and we assume that Nf<<1.
Also note that since each machine is assumed to have a throughput of .1g/s, the minimum yearly product rate
will be 1576.8 kg/year with only one machine in the last enriching stage.