Verification of the OREST (HAMMER-ORIGEN) depletion program system using post-irradiation analyses of mixed oxide fuel from the Obrigheim Reactor
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.
- Research Organization:
- Gesselschaft fuer Reaktorsicherheit (GRS) mbH, Garching (Germany)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 7777192
- Report Number(s):
- ORNL/tr-88/21; GRS-A-1085; ON: DE88017046
- Resource Relation:
- Other Information: Portions of this document are illegible in microfiche products; Related Information: Translation of the German report GRS-A-1085
- Country of Publication:
- Germany
- Language:
- English
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22 GENERAL STUDIES OF NUCLEAR REACTORS
OBRIGHEIM REACTOR
FUEL RODS
BORON
BURNUP
FISSION POISONS
H CODES
MIXED OXIDE FUELS
NUMERICAL DATA
O CODES
POST-IRRADIATION EXAMINATION
REACTOR SAFETY
URANIUM OXIDES
ACTINIDE COMPOUNDS
CHALCOGENIDES
COMPUTER CODES
DATA
ELEMENTS
ENRICHED URANIUM REACTORS
FUEL ELEMENTS
FUELS
INFORMATION
MATERIALS
NUCLEAR POISONS
OXIDES
OXYGEN COMPOUNDS
POWER REACTORS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR MATERIALS
REACTORS
SAFETY
SEMIMETALS
SOLID FUELS
THERMAL REACTORS
URANIUM COMPOUNDS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* - Power Reactors
Nonbreeding
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220900 - Nuclear Reactor Technology- Reactor Safety