FIGURE D.1 Schematic representation of the uranium-235 fission process. N = neutrons and FPs = fission products.

FIGURE D.1 Schematic representation of the uranium-235 fission process. N = neutrons and FPs = fission products.

FIGURE D.2 Production of Mo-99 from neutron capture. N = neutron.

FIGURE D.2 Production of Mo-99 from neutron capture. N = neutron.

The most commonly used alternative method for producing Mo-99 involves the neutron capture on an enriched target of Mo-98 (natural occurrence of Mo-98 is 24.13 percent), which is illustrated schematically in Figure D.2.

The fission cross section for thermal fission of U-235 is approximately 600 barns1 which represents a very high probability. Of this, approximately

1

1 barn = 1 × 10−24 cm2.



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