Verification of the OREST (HAMMER-ORIGEN) Depletion Program System Using Post-Irradiation Analyses of Mixed Oxide Fuel from the Obrigheim Reactor.

摘要

Recycling calculations for uranium dioxide (UO sub 2 ) and mixed oxide (MOX) fuel are being carried out in conjunction with Project SR 316 entitled ''Safety Analysis for Thermal Recycling in the Federal Republic of Germany.'' On the basis of the calculated nuclide inventories in spent fuel it is then possible to treat safety issues related to thermal recycling. The reliable determination of fission material quantities and their composition is therefore of particular importance. The OREST program system is used to calculate the nuclide inventories in spent LWR fuel, and a large number of boundary conditions such as reactor and fuel assembly type, burnup and fuel composition can be considered using this system. It makes it possible to carry out the recycling calculations in conjunction with Project SR 316 in a physically satisfactory way. 15 refs., 9 figs., 12 tabs. (ERA citation 13:053643)