NFCSS, An Example Case

NFCSS Example

Example Study

Nuclear Fuel Cycle consists of a set of processes and materials to be processed. There are many different fuel cycle options utilizing different nuclear materials. In order to figure out the best fuel cycle options with the most efficient use of nuclear materials, one needs to compare nuclear fuel cycle service and material requirements for different options and for different projections.

This web site is intended to give information on the capabilities of the NFCSS by providing an example case for a selected scenario. Scenario parameters and their values, assumptions in the selection of scenario, and the results of service and material requirements for the selected scenario are presented in this web publication.

Before going to the details of the selected scenario and the results, the reader should note:

  • that the selection of scenario is just based on the existing assumptions and does not reflect any official declaration from the IAEA or its Member States;
  • that the greatest care has been taken in collecting the actual data for historical operation to the extent possible;
  • that this is a theoretical calculation and might not reflect technically or practically possible options.

Main Assumptions

  • The calculations were performed for the period of 1955-2050. The year 2050 is selected for the end of calculation period, because of the increasing uncertainity on the nuclear power projections and other input parameters as well as the expected bulk introduction of the new generation nuclear power plants.
  • The historical data for the input parameters were retrieved from the IAEA databases and publications, from published authoritative reports by the other organizations/companies, or from the consultants recommendations in the order of applicability.
  • The projection of the future values for input parameters were taken from the IAEA publications, from published authoritative reports by the other organizations/companies, or from the consultants recommendations in the order of applicability.
  • The reactor types are grouped in terms of their nuclear characteristics (7 types).
  • The reactor types with significant contribution to the commercial nuclear power production were included in the example.
  • MOX fuel is assumed to be fabricated with proper mixture of depleted uranium (enrichment tails) and reprocessed Plutonium from the spent UOX fuel with 3.3% initial enrichment, 33 GWD/t discharge burnup after 5 years of cooling.