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KORIGEN

History of KORIGEN

KORIGEN was developed at FZK on the basis of the Oak Ridge Isotope Generation and Depletion code ORIGEN.

Options

Starting with a given nuclear fuel, e.g. 530 kg uranium dioxide in a subassembly of a pressurized water reactor or a certain amount of waste, KORIGEN determines the changes of the initial nuclide concentrations caused by neutron reactions during reactor operation and/or by radioactive decay. The latter, in particular, comprise the fission products, gerenerated from fissions of actinides.

Changes of the nuclide inventory during irradiation at time t depend on

  • the nuclides present at time t and
  • the neutron field impinging on the fuel at time t, represented by the neutron flux density, i.e. on the irradiation history.

For a standard burn-up calculation for fuel in an operating critical power reactor, KORIGEN may be provided with the specific thermal power of the fuel under consideration, dependent on time, i.e. with the power history. Then, the neutron flux density will be determined from the thermal power and the fission energy release.

In a second option to be used for activation and orientational transmutation studies, KORIGEN allows to enter the neutron flux history. However, general transmutation calculations are done in the standard burn-up option.

Results of KORIGEN may be listed for individual nuclides and chemical elements, dependent on time since reactor start-up and fuel discharge. For the following quantities output tables may be provided:

  • Concentrations (gramatoms)
  • Concentrations (g)
  • Radioactivities (Bq or Ci)
  • Total decay heat (W)
  • Gamma decay heat (W)
  • Ingestion radiotoxicities (realtive)
  • Inhalation radiotoxicities (relative)

Additionally, the emission and gamma radiation from irradiated fuel and from high-active waste may be calculated. (contact)